4th International Nuclear Chemistry Congress
14 – 19 September 2014, Maresias, São Paulo, Brazil
Program
Abstract Book
Edited by
Marina B. A. VASCONCELLOS
MESSAGE FROM THE
ORGANIZING COMMITTEE
The Organizing Committee of the 4th International Nuclear Chemistry Congress-4th INCC 2014 would
like to present its warmest welcome to all the participants who came to Maresias, São Paulo to honour us
with their presence.
The INCC Congress series started in 2005, after the creation of the INCS-International Nuclear Chemistry
Society, by initiative of Dr. Turan Ünak from Ege University, Izmir, Turkey.
The first INCC Congress was held in Kusadasi, Turkey in May 2005, followed by Cancún, Mexico, in April
2008 and Sicily, Italy, in September 2011.
This series of scientific events served as excellent opportunity for exchange of knowledge, for scientists from
different subject areas, where the production and investigation on the peaceful uses of radioisotopes and
nuclear radiation can contribute significantly to the technical progress of humanity.
The following themes are the focus of the 4th INCC 2014: Radiochemistry, Radiation Chemistry,
Radioanalytical Chemistry, Education in Nuclear Chemistry, Radiopharmaceutical Chemistry,
Radioecology and Geochemistry, Radiation Protection , Nuclear and Related Techniques, Nuclear Reactors
The 4th INCC 2014 will have a duration of five days, including: eleven invited talks, twelve oral sessions and
two poster sessions, with a total of more than 200 papers, from 23 countries.
Also a meeting of the International Nuclear Chemistry Society is scheduled, in the same way as it happened
in the previous congresses of the series.
We would like to thank the invited speakers for accepting to contribute to our congress and to all the
researchers who sent their papers to make possible the success of the event !
Special thanks are due to the Brazilian and international financial agencies and companies that gave
financial support to guarantee the realization of the 4th INCC 2014.
In particular, we must acknowledge the support of IPEN-CNEN/SP, CNEN-Brazilian Nuclear Energy
Commission, ABEN-Brazilian Society for Nuclear Energy and INCS-International Nuclear Chemistry
Society.
We wish all the participants a very fruitful meeting and a pleasant time in Maresias!
3
SUMMARY
Committee.............................................................................................. 06
Promotion and Sponsors......................................................................... 07
General Information............................................................................... 08
Program................................................................................................... 10
Invited Speakers...................................................................................... 12
Detailed Program.................................................................................... 14
Poster Session.......................................................................................... 18
Abstracts................................................................................................. 31
Invited Speakers............................................................................... 33
Oral Session...................................................................................... 45
Poster Session................................................................................. 119
COMMITTEE
Chair:
Marina Beatriz Agostini Vasconcellos | IPEN - CNEN/SP
Co-Chair:
Turan Ünak | Emeritus of Ege University, Izmir, Turkey
President of the International Nuclear Chemistry Society
Local Committee:
Ana Maria Graciano Figueiredo | IPEN - CNEN/SP
Casimiro J. S. Munita | IPEN- CNEN/SP
Déborah I. T. Fávaro | IPEN - CNEN/SP
Edson Gonçalves Moreira | IPEN - CNEN/SP
Maria José Armelin | IPEN - CNEN/SP
Mitiko Saiki | IPEN - CNEN/SP
Paulo S. Cardoso da Silva | IPEN - CNEN/SP
Vera Akiko Maihara | IPEN - CNEN/SP
Almir Faria Clain | IRD - CNEN/RJ
Barbara Mazzilli | IPEN - CNEN/SP
Elvis Joacir de França | CRCN/NE/PE
Maria Ângela de Menezes | CDTN - CNEN/MG
International Scientific Board:
Aleksander Bilewicz | Poland
Amares Chatt | Canada
Boris L. Zhuikov | Russia
Borut Smodis | Slovenia
Chai Zhifang | China
Eduardo Cortes Toro | Chile
Flavia Groppi | Italy
James D. Â Navratil | USA
João Osso Junior | Austria
Kattesh V. Katti | USA
Manuel Navarrete | Mexico
Maria do Carmo Freitas | Portugal
Maria Helena Sampa | Brazil
Mathias Rossbach | Germany
Namik K. Aras | Turkey
Panagiotis Misaelides | Greece
Rita Pla | Argentina
Robert Parr | Austria
Rolf Zeisler | USA
Simon Jerome | UK
Suresh K. Aggarwal | India
Tibor Braun | Hungary
Turan Ünak | Turkey
Xiaolin Hou | Denmark
6
PROMOTION
SPONSORS
SUPPORT
Conselho Nacional de Desenvolvimento Científico e Tecnológico (CNPq)
Coordenação de Aperfeiçoamento de Pessoal de Nível Superior (CAPES)
7
GENERAL INFORMATION
REGISTRATION DESK
Schedule
September 14th
September 15th
September 16th
September 18th
September 19th
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|
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4:00 pm - 7:00 pm
7:30 am - 6:30 pm
7:30 pm - 8:00 pm
8:00 pm - 8:00 pm
8:00 pm - 1:00 pm
BADGES
The use of bagde is mandatory for accessing the event.
OPENING CEREMONY AND WELCOME COCKTAIL
The Opening Ceremony will be on September 14th, starting at 6:15 pm, at Auditorium of Maresias Beach
Hotel. After the ceremony, the Welcome Cocktail will be served at the restaurant of hotel.
MEDIA DESK
The media desk is opened at the same period as the Registration Desk. The presentations should be recorded
and tested as early as possible, avoiding problems during the program presentations. The following medias will
be accepted: flash drive, CD and DVD.
POSTER SESSION
The Poster Session will be held on September 16th from 6:15 pm to 7:45 pm and on September 18th, from 6:00
pm to 7:30 pm.
Fixing material will be provided.
The author must be present during the session beside the poster, on the date of the presentation, to answer
questions of the interested people. The delivery of certificates will be done after the poster presentation.
The posters must be fixed on the presentation day, from 8:30 am and removed at the same day at the end of
presentation. The Organizing Committee is not responsible for posters that are not removed.
PRESENTATIONS ON THE WEBSITE
The Secretariat will ask from all the speakers an authorization for publishing the presentations on the website.
They will be available in PDF format from October 30th, 2014.
8
GENERAL INFORMATION
MEALS INCLUDED
The meals included in your registration are: Welcome Cocktail, coffee breaks and Conference Dinner.
LUNCH AND DINNER
The lunch break will be from 12:20 pm to 2:10 pm.
The participants hosted in Maresias Beach Hotel have lunch and dinner included in the hotel package. The
participants that are in another hotel may get the voucher for lunch and dinner at the hotel reception (BRL
50.00) each one.
There are options of restaurants in Maresias, information at the hotel reception.
INTERNET
The password for wi-fi access can be purchase at the hotel reception. Value: BRL 15.00 per day.
TOURISTIC TOURS
The Maremar Turismo Agency will attend from Setember 15th to 17th at foyer of hotel.
Phone: 55 12 3896-1418 or 3896-2443
E-mail.: [email protected]
TRANSPORT OPTIONS
Regular Group Transfer
Levitatur - Official Travel Agency
BRL 175.00 per person and route
Applications by e-mail: [email protected]
Taxi
Price: BRL 550.43 / USD 272.49 / EUR 198.71
GUARUCOOP: Phone 55 11 2440-7070
Bus
Company: Passaro Marron | Litorânea. www.passaromarron.com.br
Maresias - Guarulhos Airport
Departure Arrival 4:35 am
8:45 am
8:35 am
12:45pm
3:35 pm
8:45 pm
6:35 pm
10:55 pm
Departure: Av. Francisco Loup, 633 - Maresias
9
PROGRAM
Time
September 14th
Sunday
September 15th
Monday
September 16th
Tuesday
Uday Bhonsle
Radojko Jaćimović
Juan M. N. Tejero (Mexico)
Paulo Roberto Lima da Cruz (Brazil)
Miroslav Vetrik (Czech Republic)
Serap Teksöz (Turkey)
Robbert Van Sluijs (Netherlands)
Alberto F. Alarcón (Mexico)
Márcio Arruda Bacchi (Brazil)
Coffee break
Coffee break
Session 2 - RAC
Session 6 - RCH + RPT
Amares Chatt
Zsolt Révay
Marcelo M. Redígolo (Brazil)
Jan Kucera (Czech Republic)
Gary Richard Eppich (USA)
Massimiliano Clemenza (Italy)
Barbara P. Mazzilli (Brazil)
Marek Trojanowicz (Poland)
Jorge Eduardo de S. Sarkis (Brazil)
Traian Zaharescu (Romania)
Lunch
Lunch
Session 3 - EDU + RPH
Session 7 - NUR + REG
Turan Ünak
José Augusto Perrotta
Flavia Groppi (Italy)
Eser Uçar (Turkey)
Borut Smodiš (Slovenia)
Melissa N. Sondermann (Brazil)
Alfredo V. B. Bernedo (Brazil)
Vivianne L. Bormann (Brazil)
Session 1 - RPH
Page 34
8:30-10:10
Session 5 - NRT
Page 38
Page 71
Page 49
10:10-10:40
Page 36
10:40-12:20
Page 55
12:20-2:10
Page 42
2:10-3:50
Page 61
3:50-4:20
Registration
Page 39
Page 83
Coffee break
Session 4 - NRC + RAC
Session 8 - NRT
Maria Helena Taddei
John W. Bennett
Elena Lapshina (Russia)
Yuichi Hatsukawa ( Japan)
Valentina S. Ostapenko (Russia)
Zahily H. Fernández (Cuba)
Michael Krachler (Germany)
Ana Maria Graciano Figueiredo (Brazil)
Maria Â. B. C. Menezes (Brazil)
Patricia Socorro Bedregal Salas (Brazil)
Page 65
6:15-6:45
Page 77
Coffee break
Page 41
4:20-6:15
Page 40
Opening cerimony
Page 33
Page 89
Poster Session 1
Page 123
6:45-7:45
Welcome Cocktail
7:45-9:00
10
EDU
Education in Nuclear Chemistry
NUR
Nuclear Reactors
REG
Radioecological and Geochemistry
NRC
Nuclear and Radiochemistry
RAC
Radioanalytical Chemistry
RPH
Radiopharmaceutical Chemistry
NRT
Nuclear and Related Techniques
RCH
Radiation Chemistry
RPT
Radiation Protection
PROGRAM
Time
September 17th
Wednesday
September 18th
September 19th
Session 9 - RPT + NRT
Session 12 -RCH + REG
Thursday
Friday
Rafael García-Tenorio
Page 37
8:30-10:10
Sonia Hatsui Tatumi (Brazil)
Mehmet Kildir (Turkey)
Mary Pik Wai Chin (Canada)
Olivio Pereira de Oliveira Junior (Brazil)
Gustavo H. C. Varca (Brazil)
Paulo A. L. Ferreira (Brazil)
Dong-Yong Chung (South Korea)
Page 115
Page 97
10:10-10:40
Coffee break
Coffee break
Session 10
RAC + NRC + REG
Rolf Zeisler
Page 44
10:40-12:20
Elvis Joacir de França (Brazil)
Norbert Kavasi ( Japan)
Pasquale Avino (Italy)
André Luis Lima de Araújo (Brazil)
Poster Awarding &
Closing Cerimony
Page 103
Free day
12:20-2:10
Lunch
Session 11 - RPH
Regina Carneiro
Page 35
2:10-3:50
Mohammed Al-Quahtani (Saudi Arabia)
Ondrej Sedlacek (Czech Republic)
Serap Teksöz (Turkey)
Fazilet Z. B. Muftuler (Turkey)
Page 109
3:50-4:20
Coffee break
4:20-6:00
INCC Assembly
Poster Session 2
6:00-7:30
Page 227
8:30-0:00
Conference Dinner
EDU
Education in Nuclear Chemistry
NUR
Nuclear Reactors
REG
Radioecological and Geochemistry
NRC
Nuclear and Radiochemistry
RAC
Radioanalytical Chemistry
RPH
Radiopharmaceutical Chemistry
NRT
Nuclear and Related Techniques
RCH
Radiation Chemistry
RPT
Radiation Protection
11
INVITED SPEAKERS
Dr. John W. Bennett
Head, Center for Nuclear Applications
Australian Nuclear Science and Technology Organization - ANSTO
| Australia
Dr. Uday Bhonsle
Radiopharmaceutical Scientist at the International Atomic Energy
Agency
| Austria
Dr. Regina Carneiro
Production Manager of Radiopharmacy at IPEN-CNEN/SP Brazilian Nuclear Energy Commission
| Brazil
Dr. Amares Chatt
Adjunct Professor at Dalhousie University
| Canada
Dr. Rafael Garcia-Tenorio
Professor at the University of Sevilla
| Spain
Dr. Radojko Jaćimović
Senior Researcher at Department of Environmental Sciences
Jozef Stefan Institute
| Slovenia
12
INVITED SPEAKERS
Dr. José Augusto Perrotta
Nuclear Engineer at IPEN-CNEN/SP - Brazilian Nuclear Energy
Commission and Technical Coordinator of the Brazilian Multipurpose
Reactor - RMB
| Brazil
Dr. Zsolt Revay
Senior Research Scientist at Institute of Isotopes, Budapest and
Editor in Chief of the Journal of Radioanalytical Chemistry
| Hungary
Dr. Maria Helena Taddei
LAPOC/CNEN - Brazilian Nuclear Energy Commission
| Brazil
Dr. Turan Ünak
President of the International Nuclear Chemistry Society
| Turkey
Dr. Rolf Zeisler
Scientist Emeritus-National Institute of Standards and Technology
| USA
13
SEP 15 | Monday
Time
Activity
Session 1 - Radiopharmaceutical Chemistry
8:30-9:10
9:10-9:25
dioPharMaceuticals
Uday Bhonsle, Radiopharmaceutical Scientist, Radioisotope Products and Radiation Technology Section (RIRT), Vienna,
Austria - Page 34
FULVI-H AS HUMAN DIETARY SUPPLEMENT
Juan Manuel Navarrete Tejero, Universidad Nacional Autónoma de México - UNAM - Page 49
9:25-9:40
COMPARISON OF 99mTc ACTIVITY MEASUREMENTS AT LNMRI USING SIRTI OF THE BIPM, A NEW
INSTRUMENT FOR COMPARING SHORT-LIVED RADIONUCLIDES
Paulo Alberto Lima da Cruz, Instituto de radioproteção e Dosimetria - Page 50
9:40-9:55
New potential for treatment of Wilson`s disease
Miroslav VetríK, Institute of Macromolecular Chemistry AS CR v.v.i. - Page 51
9:55-10:10
10:10-10:40
10:40-11:20
RADIONUCLIDE LABELLED NANOPARTICLES
Serap Teksoz, Department of Nuclear Applications, Institute of Nuclear Sciences, Ege University - Page 52
Coffee Break
Session 2 - Radioanalytical Chemistry
INVITED SPEAKER - iMPortance of neutron actiVation in sPeciation analysis
Amares Chatt, Trace Analysis Research Centre, Department of Chemistry, Dalhousie University, Halifax, Canada - Page 36
11:20-11:35
COMPARATIVE STUDY OF INORGANIC ELEMENTS DETERMINATION IN WHOLE BLOOD FROM Dmdmdx/J
MICE STRAIN BY EDXRF AND NAA ANALYTICAL TECHNIQUES
Marcelo Miyada Redígolo, Instituto de Pesquisas Energéticas e Nucleares - Centro de Química e Meio Ambiente - Page 55
11:35-11:50
Sodium determination in NIST SRMs 1515 Apple Leaves and 1547 Peach Leaves by INAA: What has
happened with the sodium certified values?
Jan Kucera, Nuclear Physics Institute ASCR - Page 56
11:50-12:05
Model-Age Determination of Nuclear Forensic Materials by Mass Spectrometry
Gary Richard Eppich, Chemical Sciences Division, Lawrence Livermore National Laboratory - Page 57
12:05-12:20
LOW BACKGROUND NEUTRON ACTIVATION ANALYSIS: A POWERFUL TOOL FOR ENVIRONMENTAL
SCIENCES AND PHYSICS OF RARE EVENTS
Massimiliano Clemenza, Physics Department, University of Milano-Bicocca, 2INFN sezione di Milano Bicocca - Page 58
12:20-2:10
LUNCH
Session 3 - Education in Nuclear Chemistry and Radiopharmaceutical Chemistry
2:10-2:50
INVITED SPEAKER - the Present status of nuclear cheMistry education in different
uniVersities and countries
Turan ÜnaK, International Nuclear Cheistry Society (INCS), Izmir, Turkey - Page 42
2:50-3:05
RADON INDOOR MEASUREMENTS A WAY TO EDUCATE TO NUCLEAR ISSUE: ITALIAN RADIOLAB PROJECT
Flavia Groppi, Università degli Studi di Milano & INFN, Physics Department - LASA Laboratory - Page 61
3:05-3:20
NANOSTRUCTURED LIPID CARRIER DESIGN FOR IMAGING AND TARGETED PACLITAXEL DELIVERY
Eser Uçar, Ege University Institute of Nuclear Sciences - Page 62
3:20-4:20
14
INVITED SPEAKER - international atoMic energy agency (iaea) PrograMs in the area of Ra-
Coffee Break
sesion 4 - Nuclear and Radiochemistry and Radioanalytical Chemistry
4:20-5:00
INVITED SPEAKER - radiocheMistry techniQues used in characteriZation of radioactiVe Wastes
5:00-5:15
RECOVERY OF ACTINIUM-225 AND RADIUM-223 FROM NATURAL THORIUM IRRADIATED WITH PROTONS
Elena V. Lapshina, Institute for Nuclear Research Russian Academy of Sciences - Page 65
5:15-5:30
Prodcution of 99Mo/99mTc generator using high specific activity of 99Mo recoiled out from
molybdenum nanoparticles target by the 100Mo(n,2n)99Mo reaction
Yuichi Hatsukawa, Japan Atomic Energy Agency - Page 66
5:30-5:45
SEPARATION OF 225Ac FROM RARE EARTH ELEMENTS GENERATED BY PROTON IRRADIATION OF NATURAL
THORIUM
Valentina S. OSTAPENKO, Chemistry Department, Lomonosov Moscow State University - Page 67
Maria Helena Taddei, Comissão Nacional de Energia Nuclear – Laboratório de Poços de Caldas, Poços de Caldas, Brazil - Page 41
SEP 16 | Tuesday
Time
Activity
session 5 - Nuclear and Related Techniques
8:30-9:10
INVITED SPEAKER - Metrology in cheMistry at the iJs/o-2: adVantages and disadVantages
9:10-9:25
Evaluation of Westcott g(Tn)-factors for k0-NAA using non-1/v nuclides
Robbert van Sluijs, k0-ware - Page 71
9:25-9:40
LEAD ISOTOPIC RATIOS IN ENVIRONMENTAL SAMPLES AS ORIGIN MARKERS
Alberto Fernández Alarcón, Facultad de Química, Edificio D, Universidad Nacional Autónoma de México - Page 72
9:40-9:55
Assessing total potassium in forest soils by measuring 40K
Márcio Arruda BacchI, Center for Nuclear Energy in Agriculture - Page 73
9:55-10:40
Radojko JAĆIMOVIĆ, Department of Environmental Sciences, Jožef Stefan Institute, Ljubljana, Eslovenia - Page 38
Coffee Break
session 6 - Radiation Chemistry
10:40-11:20
INVITED SPEAKER - high-flux ProMPt-gaMMa actiVation analysis at frM ii, garching
11:20-11:35
LIXIVIATION OF METALS IN COLUMNS OF TROPICAL SOIL AMENDED WITH PHOSPHOGYPSUM
Barbara P. Mazzilli, Laboratório de Radiometria Ambiental, Instituto de Pesquisas Energéticas e Nucleares (IPEN) - Page 77
Zsolt révay, Technische Universität München, Forschungsneutronenquelle Heinz Maier-Leibnitz - Page 40
11:35-11:50
Radiolytic decomposition of environmentally persistant perfluorinated surfactants
with the use of ionizing radiation
Marek Trojanowicz, Department of Chemistry, University of Warsaw, Institute of Nuclear Chemistry and Technology Dorodna - Page 78
11:50-12:05
BUILDING A NUCLEAR FORENSIC ANALYSIS CAPABILITY IN BRAZIL
Jorge Eduardo de Souza Sarkis, Instituto de Pesquisas Energéticas e Nucleares - Page 79
12:05-12:20
RADIATION EFFECTS IN PA6/EPDM BLENDS
Traian Zaharescu, INCDIE ICPE CA, Department of Advanced Materials - Page 80
12:20-2:10
2:10-2:50
LUNCH
session 7 - Nuclear Reactors and Radioecological and Geochemistry
INVITED SPEAKER - BraZilian MultiPurPose reactor, a structuring enterPrise for the
nuclear area
José Augusto Perrotta, Comissão Nacional de Energia Nuclear, São Paulo, Brazil - Page 39
2:50-3:05
TRANSFER OF URANIUM AND RADIUM TO CHINESE CABBAGE FROM SOIL CONTAINING ELEVATED LEVELS
OF NATURAL RADIONUCLIDES
Borut SMODIŠ, Jožef Stefan Institute - Page 83
3:05-3:20
KINETICS SORPTION OF METAL RADIOTRACERS IN THE WATER-SEDIMENT INTERFACE OF A HIGHLY
CONTAMINATED COASTAL AREA (SEPETIBA BAY, RIO DE JANEIRO, BRAZIL)
Melissa Nogueira Sondermann, Departamento de Geoquímica, Universidade Federal Fluminense (UFF) - Page 84
3:05-3:20
RADIOGRAPHY APLLIED TO FUNERAL AND UTILITY ARCHAEOLOGICAL CERAMICS STUDIES
Alfredo Victor Bellido Bernedo, Instituto de Química. Universidade Federal Fluminense - Page 85
3:20-3:35
3:35-3:50
4:20-5:00
5:00-5:15
BIOAVAILABILITY OF TRACE METALS IN SEDIMENTS: A REVIEW
Vivianne Lúcia Bormann de Souza, CNEN/CRCN - Page 86
Coffee Break
session 8 - Nuclear and Related Techniques
INVITED SPEAKER - Managing naa in the Multi-PurPose oPal research reactor -
oPPortunities and challenges
John W. Bennett, Australian Nuclear Science and Technology Organisation (ANSTO), Lucas Heights, Australia - Page 33
MULTIELEMENT ANALYSIS OF LICHEN SAMPLES USING XRF METHODS. COMPARISON WITH ICP-AES AND FAAS
Zahily Herrero Fernández, Centre for Technological Applications and Nuclear Development (CEADEN) - Page 89
5:15-5:30
CHALLENGES IN THE QUALITY ASSURANCE OF ELEMENTAL AND ISOTOPIC ANALYSES IN THE NUCLEAR
DOMAIN BENEFITTING FROM HIGH RESOLUTION ICP-OES AND SECTOR FIELD ICP-MS
Michael Krachler, European Commission - Joint Research Centre, Institute for Transuranium Elements - Page 90
5:30-5:45
ASSESSMENT OF METAL ATMOSPHERIC POLLUTION DURING AND AFTER THE CONSTRUCTION OF A
PERIPHERAL HIGHWAY USING TILLANDSIA USNEOIDES AS BIOMONITOR
Ana Maria Graciano Figueiredo, Instituto de Pesquisas Energéticas e Nucleares, IPEN - CNEN/SP - Page 91
5:45-6:00
SPATIAL DISTRIBUTION OF NEUTRON FLUX IN GEOLOGICAL LARGE SAMPLE ANALYSIS AT CDTN/CNEN, BRAZIL
Maria Ângela de Barros Correia Menezes, Nuclear Technology Development Centre, Brazilian Comission for Nuclear Energy,
Laboratoy for Neutron Activation Analysis, CDTN/CNEN - Page 92
6:00-6:15
THE WARI INFLUENCE IN THE SOUTH OF PERU: PROVENANACE STUDY OF THE MIDDLE HORIZON
POTERRY FOUND IN THE ARCHEOLOGICAL SITE, LA REAL, USING k0-INAA
Patricia Socorro Bedregal Salas, División de Técnicas Analíticas Nucleares, Instituto Peruano de Energía Nuclear - Page 93
6:15-7:45
Poster Session 1
15
SEP 18 | Thursday
Time
Activity
session 9 - Radiation Protection and Nuclear and Related Techniques
8:30-9:10
9:10-9:25
The use of Luminescence emission of 3Al2O3-2SiO2: Er phosphors for environmental
dosimetry
Sonia Hatsue Tatumi, Departamento de Ciência do Mar, Universidade Federal de São Paulo, Santos, Brasil - Page 97
9:25-9:40
INDOOR RADON CONCENTRATIONS AT UNIVERSITY CAMPUS AND HOUSES AT TWO DISTRICTS OF
ANKARA,TURKEY
Mehmet Kıldır, Department of Basic Sciences, Faculty of Arts and Sciences, Istanbul Kemerburgaz University - Page 98
9:40-9:55
A BRIEF RADIATION HISTORY OF THE FUTURE ULTRA COLD NEUTRON FACILITY AT TRIUMF
Mary Pik Wai CHIN, TRIUMF - Page 99
9:55-10:10
10:10-10:40
10:40-11:20
CHEMICAL, RADIOCHEMICAL, SPECTROCHEMICAL AND ISOTOPIC CHARACTERIZATION OF URANIUM
HEXAFLUORIDE USED IN THE PREPARATION OF NUCLEAR REACTOR FUEL
Olivio Pereira de Oliveira Junior, Instituto de Pesquisas Enérgeticas e Nucleares (IPEN-CNEN/SP) - Page 100
Coffee Break
session 10 - Radioanalytical Chemistry, Nuclear and Radiochemistry and
Radioecological and Geochemistry
INVITED SPEAKER - the use of inaa in the deVeloPMent and certification of nist
Biological standard reference Materials
Rolf Zeisler, National Institute of Standards and Technology, Gaithersburg, USA - Page 44
11:20-11:35
ECOLOGICAL STOICHIOMETRY APPLIED TO SYSTEMATIC BOTANY OF TREE FAMILIES FROM CERRADO
AND ATLANTIC FOREST
Elvis Joacir de FRANÇA, Divisão de Pesquisa e Desenvolvimento, Centro Regional de Ciências Nucleares do Nordeste, Comissão
Nacional de Energia Nuclear - Page 103
11:35-11:50
A NEW APPROACH TO Sr-90 MEASUREMENT USING DGA RESIN
Norbert KAVASI, National Institute of Radiological Sciences - Page 104
11:50-12:05
PHYSIOLOGICAL AND BEHAVIORAL PARAMETERS AFFECTING THE HAIR ELEMENT CONTENT OF YOUNG
ITALIAN POPULATION
Pasquale Avino, DIPIA, INAIL settore Ricerca - Page 105
12:05-12:20
Determination of natural radionuclides 40k, eU and eTh in environmental samples from the
vicinity of Aramar Experimental Center, Brazil
André Luis Lima de Araújo, Navy Technology Center in Sao Paulo - Page 106
12:20-2:10
LUNCH
session 11 - Radiopharmaceutical Chemistry
2:10-2:50
INVITED SPEAKER - radioPharMaceuticals Production at iPen/cnen-sP
2:50-3:05
A comparison study of several radioiodinated intermediates for labelling short peptides
Mohammed Al-Qahtani, Ciclotron and Radiopharmaceuticals Department, KFSH&RC - Page 109
3:05-3:20
POLYMER CONJUGATES OF AUGER ELECTRON EMITTER BEARING ELLIPTICINES FOR TARGETED CANCER
THERAPY
Ondrej Sedlacek, Institute of Macromolecular Chemistry, Czech Academy of Sciences, v.v.i. - Page 110
3:20-3:35
RADIOLABELED NANOPARTICLES AND RECENT APPROACHES
Serap Teksöz, Ege University, Institute of Nuclear Sciences, Department of Nuclear Applications - Page 111
3:35-3:50
A PERSPECTIVE ON PLANT ORIGIN RADIOLABELED COMPOUNDS, THEIR BIOLOGICAL AFFINITIES AND
INTERACTION BETWEEN PLANT EXTRACTS WITH RADIOPHARMACEUTICALS
Zumrut Fazilet Biber Muftuler, Institute of Nuclear Science, Ege University - Page 112
3:50-4:20
16
INVITED SPEAKER - ManageMent of By-Products generated By norM industries: toWards
their ValoriZation and MiniMiZation of their enVironMental iMPact
Rafael García-tenorio, Centro Nacional de Aceleradores (Universidad Sevilla, J. Andalucía, CSIC), Sevilla, Spain - Page 37
Regina carneiro, Radiopharmacy Center, Instituto de Pesquisas Energéticas e Nucleares - IPEN-CNEN/SP, São Paulo, Brazil - Page 35
Coffee Break
4:20-6:00
INCC Assembly
6:00-7:30
Poster Session 1
8:30-0:00
Conference Dinner
SEP 19 | Friday
Time
Activity
session 12 - Radiation Chemistry and Radioecological and Geochemistry
9:25-9:40
9:40-9:55
9:55-10:10
SYNTHESIS OF PAPAIN NANOPARTICLES USING E-BEAM AND GAMMA IRRADIATION: A RADIATION
CHEMISTRY APPROACH
Gustavo Henrique Costa Varca, Instituto de Pesquisas Energéticas e Nucleares - Page 115
Model of diffusion-convection of 137Cs for the determination of recent sedimentation
rates
Paulo Alves de Lima Ferreira, Instituto Oceanográfico, Universidade de São Paulo (IO-USP) - Page 116
DECOMPOSITION OF URANYL PEROXO-CARBONATO COMPLEX IONS IN THE PRESENCE OF METAL OXIDES
IN CARBONATE MEDIA
Dong-Yong CHUNG, Korea Atomic Energy Research Institute - Page 117
10:10-10:40
Coffee Break
10:40-12:20
Poster Awarding & Closing Cerimony
17
POSTER SESSION
1 - SEP 16 | Tuesday
Education in Nuclear Chemistry
NEUTRON ACTIVATION ANALYSIS AND ITS APPLICATION TO DETERMINE THE CONCENTRATION OF ELEMENTS IN COMPLEX
MATRICES
Valerian LOBO1, 1Wollo University................................................................................................................................................................................................. 123
Knowledge about nuclear energy and radioactivity of senior high school students
Aline Sabastiane Gonçales Ramos de Oliveira1, Lucio Leonardo1-2, Sandra Regina Damatto1, 1Laboratório de Radiometria Ambiental - Instituto de
Pesquisas Energéticas e Nucleares (IPEN / CNEN) São Paulo, SP, 2 Universidade Paulista - UNIP............................................................................................... 124
Nuclear and Radiochemistry
MECHANISM OF UO2(NO3)2×6H2O DECOMPOSITION UNDER MICROWAVE IRRADIATION
Sergey A. KULYUKHIN1 , 1Institute of Physical Chemistry and Electrochemistry, Russian Academy of Science........................................................................ 127
SORPTION OF UO22+ ON SORBENTS BASED ON MODIFIED SILICA GEL CONTAINING Cu, Ni, AND Zn FROM AQUEOUS SOLUTIONS
Sergey A. KULYUKHIN1, Margarita P. GORBACHEVA1 , 1Frumkin Institute of Physical Chemistry and Electrochemistry, Russian Academy of Science.................128
FORMATION OF NITROGEN OXIDES DURING URANIUM NITRIDE DISSOLUTION IN NITRIC ACID
Alexei A. Bessonov1, Sergey A. KULYUKHIN2, Andrey Yu. Shadrin3, Yulia A. Voskresenskaya4, Oleg A. Ustinov5 , 1Frumkin Institute of
Physical Chemistry and Electrochemistry, Russian Academy of Science, 2IOpen joint-stock company VNIINM......................................................................... 129
ABSORPTION OF NITROUS OXIDE IN AQUEOUS SOLUTIONS OF GAS CLEANING SYSTEM IN TECHNOLOGICAL SCHEMES OF UN
DISSOLUTION
Sergey A. KULYUKHIN1, Andrey Yu. Shadrin2, Alexei A. Bessonov1, Yulia A. Voskresenskaya2, Oleg A. Ustinov2, , 1Frumkin Institute of
Physical Chemistry and Electrochemistry, Russian Academy of Science, 2IOpen joint-stock company VNIINM......................................................................... 131
Np(V)-PHENANTHROLINE-DiCARBOXYLIC ACID COMPOUNDS:
SYNTHESIS, STRUCTURE, PROPERTIES
Alexei A. Bessonov1, A.B. Yusov1, I. A. Charushnikova1, A. M. Fedosseev1, 1Frumkin Institute of Physical Chemistry and Electrochemistry, Russian
Academy of Sciences..................................................................................................................................................................................................................................................133
Uranyl Nitrate Hydrolytic Behavior in the Presence of Reductant
Alexei A. Bessonov1, A.M. Fedosseev1, Y.M. Kulyako2, S.A. Perevalov2, A.Yu. Shadrin3 , 1Frumkin Institute of Physical Chemistry and
Electrochemistry of RAS, 2Vernadsky Institute of Geochemistry and Analytical Chemistry of RAS, 3Open joint-stock company VNIINM................................ 134
Nuclear and Related Techniques
CRYSTALLINE STRUCTURE AND OXYGEN STOICHIOMETRY OF THE Ba0.50Sr0.50Co0.80Fe0.20O3-d POWDERS OBTAINED BY EDTA-CITRATE
METHOD MEASURED BY X-RAY AND NEUTRON DIFFRACTION
Everton Bonturim1, Nelson Batista de Lima1, Vera Lúcia Mazzocchi1, Carlos Benedicto Ramos Parente1, José Mestnik Filho1, Emília Satoshi
Miyamaru Seo1, 1Instituto de Pesquisas Energéticas e Nucleares IPEN-CNEN/SP....................................................................................................................... 137
EVALUATION OF A 99mTc COMPLEX AS AN OIL MULTIPHASE RADIOTRACER
Martha Sahylí Ortega Pijeira1, Judith DOMÍNGUEZ1, Jorge L. BATISTA1, Yuniel TEJEDA1, Ernesto Martínez Baez1, Jorge Borroto Portela1,
1
Department of Radiochemistry, High Institute of Applied Sciences and Technologies.................................................................................................................. 138
VARIATIONS ON UO2-DOPED AND UNDOPED FUEL PELLETS MICROSTRUCTURES BY THE ADDITION OF RECYCLED MATERIAL
Diogo Ribeiro Costa1, Franciole José Ezequiel1, Rodrigo Aparecido Barbosa1, João Paulo Rodrigues Carnaval1, 1 Brazilian Nuclear Industries
(Indústrias Nucleares do Brasil S.A.– INB)...................................................................................................................................................................................... 139
HETEROGENEITY EVALUATION OF UO2 PELLETS TO BE USED IN A BRAZILIAN MEASUREMENTS SYSTEMS INTERCOMPARISON
PROGRAMS
Bárbara Fernandes Gonçalves Cristiano1, José Ubiratan Delgado1, José Wanderley S. da Silva1, Aline Gonzalez Viana1, Fábio Cordeiro Dias1,
Marcos Sodre Grund1, Ricardo Tadeu Lopes1, 1Comissão Nacional de Energia Nuclear (CNEN), Instituto de Radioproteção e Dosimetria (IRD/CNEN)... 140
CONCEPTION AND CONSTRUCTION OF A REMOTE PROBE FOR A PORTABLE SPECTROMETER USING THE ENERGY DISPERSIVE
X-RAY FLUORESCENCE TECNIQUE
Francisco Antonio Brandão Junior1-2, Arno Heeren de OLIVEIRA1, Antonella LOMBARDI Costa1, 1Departamento de Engenharia Nuclear, Universidade
Federal de Minas Gerais, 2Centro Federal de Educação Tecnológica de Minas Gerais (CEFETMG)............................................................................................. 141
18
METAL CONTAMINATION IN SOIL OF A SCRAPYARD OF IMPOUNDED VEHICLES
Camila Neves Lange1, Ana Maria Graciano Figueiredo1, Jacinta Enzweiler2, 1Instituto de Pesquisas Energéticas e Nucleares, IPEN- CNEN/SP,
2
Instituto de Geociências, UNICAMP.............................................................................................................................................................................................. 142
MEASUREMENTS STUDIES OF ACTIVITY AND GAMMA EMISSION PROBABILITIES FOR 235U and 238U
Ronaldo Lins da Silva1, R. POLEDNA1, J. U. DELGADO1, Maria Candida Moreira de Almeida2, R. N. ALVES3, J. S. ESTRADA3, 1Laboratório Nacional
de Metrologia das Radiações Ionizantes, IRD, 2 Dinor, Comissão Nacional de Energia Nuclear -RJ, 3Instituto Militar de Engenharia, Seção Eng. Nuclear....... 143
Long-Term Performance Assessment of HPGe detectors used in the Neutron Activation Analysis (LAN) of IPENCNEN/SP (Brazil)
Guilherme Soares Zahn1, Frederico Antonio Genezini1, Regina Beck Ticianelli1, Mitiko Saiki1, 1Instituto de Pesquisas Energéticas e Nucleares (IPENCNEN/SP)......................................................................................................................................................................................................................................... 144
NATURAL RADIOACTIVITY IN WALL PAINTS: PRELIMINARY RESULTS
Leandro Milhomens da Fonseca1, Brigitte Roxana Soreanu Pecequilo1, 1Instituto de Pesquisas Energéticas e Nucleares145
USE OF ICP-MS FOR DETERMINATION OF URANIUM AND THORIUM IN SOIL SAMPLES
Helena Eugênia Leonhardt Palmieri1, Sarah Andresa Bonfim2, Fernanda José Augusto Ferreira2, 1Centro de Desenvolvimento da Tecnologia Nuclear
(CDTN/CNEN), 2Bolsista de Iniciação Científica CDTN/CNEN.................................................................................................................................................... 146
EXPERIMENTAL DESIGN APPLIED FOR THE OPTIMIZATION OF INAA METHODS
Robson Petroni1, Edson Gonçalves MOREIRA1, 1Instituto de Pesquisas Energéticas e Nucleares, IPEN - CNEN/SP............................................................. 147
TDCR AND CIEMAT/NIST LIQUID CINTILLATION METHODS FOR 3H, 14C, 99TC AND 68Ge/68Ga ACTIVITY STANDARDIZATION IN
RADIONUCLIDE METROLOGY
Paulo Alberto Lima da CRUZ1, Carlos José da Silva1, Akira Iwahara1, Jamir dos Santos Loureiro1, Antônio Eduardo de Oliveira1, Luiz Tauhata1,
Ricardo Tadeu Lopes2, 1Instituto de Radioproteção e Dosimetria/Comissão Nacional de Energia Nuclear (IRD/CNEN), 2Programa de Engenharia Nuclear,
Universidade Federal do Rio de Janeiro (PEN/COPPE, UFRJ)....................................................................................................................................................... 148
BOVINE KIDNEY REFERENCE MATERIAL PREPARATION PROPOSAL TO BE USED IN QUALITY ASSURANCE OF CHEMICAL
MEASUREMENTS IN MEAT PRODUCTS
Liliana Castro1, Edson Gonçalves MOREIRA1, Vera Akiko MAIHARA1, Marina Beatriz Agostini Vasconcellos1, 1Instituto de Pesquisas Energéticas e
Nucleares – IPEN-CNEN/SP............................................................................................................................................................................................................ 149
ELEMENTAL DETERMINATION IN Canoparmelia texana LICHEN SPECIES USING X-RAY FLUORESCENCE SPECTROMETRY
Rosiana Rocho ROCHA1, Mitiko Saiki1, Nemitala Added2, Frederico Antonio Genezini1, 1Instituto de Pesquisas Energéticas e Nucleares, IPEN-CNEN/
SP, 2Instituto de Física - Universidade de São Paulo........................................................................................................................................................................ 150
DOSIMETRIC STUDY FOR IRRADIATION PROCESSING OF CHESTNUT FRUITS: EXPERIMENTAL SETUP AND DOSE VALIDATION
Amilcar Lopes Antonio1-2-3, Isabel C. F. R. Ferreira1, Albino Bento1, M. Luisa Botelho2, Begoña Quintana3, 1CIMO/ESA, Instituto Politécnico
de Bragança, 2Centro de Ciências e Tecnologias Nucleares, IST, Universidade de Lisboa, 3Departamento de Física Fundamental, Universidad de Salamanca.. 151
Evaluation of Cl, K, Mg, Mn and Na in food groups of São Paulo Total Diet
Jéssica Braga Ambrogi1, Roseane Pagliaro Avegliano1, Uanda Paula de Medeiros dos Santos1, Vera Akiko MAIHARA1, 1Instituto de Pesquisas
Energéticas e Nucleares (IPEN/CNEN-SP)...................................................................................................................................................................................... 152
Preliminary archaeometric study of the archaeological site of Lapa Grande de Taquaraçu
Diego Renan Giglioti Tudela1, Astolfo G. M. Araujo2, Sonia Hatsue Tatumi3, Juan C. R. Mittani3, Casimiro S. Munita1, 1Instituto de Pesquisas
Energéticas e Nucleares (IPEN–CNEN/SP), 2Museu de Arqueologia e Etnologia, Universidade de São Paulo (USP), 3Universidade Federal de São Paulo
(UNIFESP)........................................................................................................................................................................................................................................ 153
ARCHAEOMETRIC STUDIES OF CERAMICS FROM THE SÃO PAULO II ARCHAEOLOGICAL SITE
Rogério Baria RIBEIRO1, Nilo F. CANO1, Shigueo Watanabe2, Sonia Hatsue Tatumi3, Eduardo Góes Neves4, Casimiro S. MUNITA1, 1Instituto de
Pesquisas Energéticas e Nucleares, IPEN-CNEN/SP, Brazil, 2Instituto de Física, Universidade de São Paulo, SP, Brazil, 3Universidade Federal de São Paulo,
Baixada Santista, SP, Brazil, 4Museu de Arqueologia e Etnologia, Universidade de São Paulo.......................................................................................................... 154
SPATIAL DOSE DISTRIBUTION IN A SYNTHETIC BREAS ON A THORAX PHANTOM INDUCIED BY SODIUM PERTECNETATE-99mTc
(Na99mTcO4-) SILICON BALLON
Carla Flávia de Lima1-2, Tarcisio Passos Ribeiro de Campos1, 1Programa de Ciências e Técnicas Nucleares do Departamento de Engenharia Nuclear,
Escola de Engenharia, Universidade Federal de Minas Gerais, 2Ecograf - Núcleo de Diagnóstico Cardiovascular S/C Ltda................................................. 155
INORGANIC ELEMENTS IN SUGAR SAMPLES CONSUMED IN SEVERAL COUNTRIES
Paula Maria Borges de Salles1, Maria Ângela de Barros Correia Menezes2, Tarcisio Passos Ribeiro de Campos1, 1Universidade Federal de Minas Gerais
(UFMG), Departamento de Engenharia Nuclear (DEN), 2Centro de Desenvolvimento da Tecnologia Nuclear/Comissão Nacional de Energia Nuclear (CDTN/
CNEN), Serviço de Reator e Técnicas Analíticas (SERTA)............................................................................................................................................................. 156
MEASUREMENTS OF TRACE ELEMENTS IN VOLCANIC LAVAS
Pedro Vinicius Guillaumon1, Eric B Norman2, Keenan J Thomas3, Paulo R Pascholati4, Tufic Madi Filho5, Iuda D Goldman vel Lejbman6,
1
Universidade de São Paulo, 2University of California at Berkeley, 3University of California at Berkeley, 4Universidade de São Paulo, 5Universidade de São
Paulo, 6Universidade de São Paulo................................................................................................................................................................................................... 157
19
QUALITY ASSESSMENT OF THE FLUOXETINE DRUG MANIPULATED IN THE CITY OF BELO HORIZONTE, BRAZIL
Alexandre Soares Leal1, Fernanda Peixoto Sepe1, Tatiana Cristina Bomfim Gomes1, Mitiko Saiki2, 1Centre for Development of Nuclear Technology
(CDTN), Brazilian Commission for Nuclear Energy (CNEN), 2Nuclear and Energy Research Institute (IPEN), Brazilian Commission for Nuclear Energy
(CNEN)............................................................................................................................................................................................................................................. 158
CYCLOTRON PARAMETERS FOR C-11 YIELD
Gustavo Lobato Campos1, Tarcísio Passos Ribeiro de Campos1, 1Escola de Ciências e Técnicas Nucleares, Universidade Federal de Minas Gerais............ 159
NAA AND XRF TECHNIQUE SEDIMENT ASSESSMENT FOR MAJOR AND TRACE ELEMENTS - TIETÊ RIVER, SÃO PAULO STATE,
BRAZIL
Flávio R. Rocha1, Paulo S. Cardoso da SILVA1, Lucas M. Castro1, Sonia Maria Barros de Oliveira2, Déborah I. T. FÁVARO1, 1Neutron Activation
Analysis Laboratory (LAN/CRPQ), IPEN/CNEN, 2Geoscience Institut, São Paulo University..................................................................................................... 160
INVESTIGATION OF WEAR METALS IN BIOFUEL VEHICLES LUBRICATING OILS BY ENERGY DISPERSIVE X-RAY FLUORESCENCE
SPECTROMETRY
Rogério Alves de Sousa REIS1, Vera Lúcia Ribeiro Salvador1, Ivone Mulako Sato1, 1Instituto de Pesquisas Energéticas e Nucleares, IPEN - CNEN/SP....... 161
X-RAY FLUORESCENCE TECHNIQUES APPLIED TO CHEMICAL CHARACTERIZATION IN PRESERVED WOODS (eucaliptus ssp)
Sergio Matias Pereira Junior1, Vera Akiko MAIHARA2, Edson Gonçalves Moreira2, Vera Lúcia Ribeiro Salvador2, Ivone Mulako Sato2, 1Instituto de
Pesquisas Tecnológicas de São Paulo - IPT, 2Instituto de Pesquisas Energéticas e Nucleares, IPEN - CNEN/SP.......................................................................... 162
CORROSION OF TiO2-COATED STAINLESS STEELS STUDIED BY ELECTROCHEMICAL TESTS AND NEUTRON ACTIVATION ANALYSIS
Olandir Vercino Correa1, Mara Cristina L. de Oliveira2, Renato Altobelli Antunes3, Mitiko Saiki1, Edval Gonçalves de Araújo4, Marina Fuser
Pillis1, 1Nuclear and Energy Research Institute, IPEN-CNEN/SP, Materials Science and Technology Center, 2Electrocell Ind. Com. Equip. Elétricos LTDA,
3
Federal University of ABC (UFABC), 4Prest Vácuo Ltda............................................................................................................................................................... 163
FEASIBILITY OF NIOBIUM OXIDE-BASED FILMS TO PREVENT CORROSION OF AISI 304 STAINLESS STEEL IN NUCLEAR FUEL
REPROCESSING PLANTS
Olandir Vercino Correa1, Mara Cristina L. de Oliveira2, Renato Altobelli Antunes3, Mitiko Saiki1, Oswaldo Pereira Vilela da Silva Junior4, Marina
Fuser Pillis1, 1Nuclear and Energy Research Institute, IPEN-CNEN/SP, Materials Science and Technology Center, 2Electrocell Ind. Com. Equip. Elétricos
LTDA., 3Federal University of ABC (UFABC), 4Prest Vácuo Ltda................................................................................................................................................. 164
Instrumental Neutron Activation Analysis of Bidens pilosa, a medicinal plant used for diabetes treating.
Rodolfo Daniel Moreno Reis Gonçalves1, Paulo S. Cardoso da SILVA1, 1Instituto de Pesquisas Energéticas e Nucleares IPEN - CNEN/SP........................ 165
Radioanalytical Chemistry
Study of potassium content in Mexican Nopal (opuntia ficus indica), by nuclear methodology using the Gamma
Spectrometry
Guillermo Espinosa1, Jose-Ignacio Golzarri1, Edgar Padilla-Soriano2, Juan Manuel Navarrete Tejero3, Trinidad Martínez Castillo3, 1Instituto de
Física, Universidad Nacional Autónoma de México. Circuito de la Investigación Científica, 2Facultad de Química, Universidad Nacional Autónoma de México.
Ciudad Universitaria, 3Facultad de Química, Universidad Nacional Autónoma de México. Edificio D, Ciudad Universitaria...................................................... 169
ARSENIC SPECIES IN FRESH-WATER AND MARINE FISH LIPIDS BY CHEMICAL SEPARATION AND NEUTRON ACTIVATION
Youqing Shi1-2, Amares CHATT1, 1Trace Analysis Research Centre, Department of Chemistry, Dalhousie University, 2Atomic Energu of Canada Limited...... 170
Determination of uranium traces in nuclear reactor IEA-R1 pool water
Adonis Marcelo SALIBA-SILVA1, Eneas Tavares de Oliveira1, Olair dos Santos1, Michelangelo Durazzo1, 1Instituto de Pesquisas Energéticas e
Nucleares (IPEN/CNEN-SP)............................................................................................................................................................................................................ 171
CESIUM ACCUMULATION IN PLANTS FROM BRAZILIAN BIODIVERSITY HOTSPOTS
Elvis Joacir de FRANÇA1, Elisabete A. De Nadai Fernandes2, Marcia Valéria de Fátima da Encarnação Sá Miranda1, Rebeca da Silva Cantinha1,
1
Divisão de Pesquisa e Desenvolvimento, Centro Regional de Ciências Nucleares do Nordeste, Comissão Nacional de Energia Nuclear, 2Radioisotopes
Laboratory, Centro de Energia Nuclear na Agricultura, Universidade de São Paulo....................................................................................................................... 172
Activity levels of gamma-emitters and barium concentrations in Brazil nuts
Maria José A. ARMELIN1, Vera Akiko MAIHARA1, Silvia Maria Franciscato Cozzolino2, Paulo S. Cardoso da SILVA1, Mitiko Saiki1, 1Instituto de
Pesquisas Energéticas e Nucleares (IPEN / CNEN – SP), 2Faculdade de Ciências Farmacêuticas, Universidade de São Paulo (USP)
A study on elemental composition of tree barks for using in atmospheric pollution monitoring
Eliane Conceição dos Santos1-2, Mitiko Saiki1, 1Instituto de Pesquisas Energéticas e Nucleares, IPEN-CNEN/SP, 2Instituto de Química, Universidade de São
Paulo................................................................................................................................................................................................................................................. 174
Assessment of Fountain Water Quality of Towns of the Iron Quadrangle, Brazil
Cláudia Alves Ferreira1, Helena Eugênia Leonhardt Palmieri1, Maria Ângela de B. C. MENEZES1, 1Centro de Desenvolvimento da Tecnologia Nuclear/
Comissão Nacional de Energia Nuclear, CDTN/CNEN................................................................................................................................................................... 175
The influence of sample properties and sample geometry on the accuracy of the gamma-ray spectrometry.
Eliane C. dos Santos1-2, Rodrigo K. Kawassaki1-2, Thais S.P. Neto1-3, Frederico Antonio Genezini1, Mitiko Saiki1, 1Instituto de Pesquisas Energéticas
e Nucleares- IPEN-CNEN/SP, 2Instituto de Química, Universidade de São Paulo, 3Faculdades Oswaldo Cruz............................................................................ 176
20
MAJOR ELEMENTAL FEATURES OF A PORTUGUESE BREAD-WHEAT ARCHIVAL COLLECTION, DETERMINED BY INSTRUMENTAL
NEUTRON ACTIVATION ANALYSIS
Catarina Isabel Alves Lourenço Galinha1-2-4, Adriano M. G. Pacheco2, Maria do Carmo Freitas1, Ana R. P. Costa3, Nuno M. B. Pinheiro3,
Benvindo Maçãs3, Ana Sofia Almeida3, Hubert T. Wolterbeek4, 1URSN/CTN-IST, University of Lisbon, 2CERENA-IST, University of Lisbon,
3
INIAV, National Institute of Agricultural and Veterinary Research, Savavém, 4Department of Radiation Science and Technology, Faculty of Applied Sciences,
Delft University of Technology Portugal.......................................................................................................................................................................................... 177
Radiation Chemistry
IMPROVEMENT IN THE RADIATION STABILITY OF EPDM/INCORPORATED EPDM POWDER/CARBON BLACK COMPOUND
Ludmila de Ysasa Pozzo Kiyan1, Traian Zaharescu2, Duclerc Fernandes Parra1, Ademar Benévolo Lugão1, 1IPEN, Center of Chemistry and
Environment, 2INCDIE ICPE CA, Department of Advanced Materials.......................................................................................................................................... 181
SIMULTANEOUS USE OF ANION EXCHANGER AND SR RESIN FOR EFFICIENT STRONTIUM ISOLATION FROM COMPLEX MATRICES
Gorana Karanović1, Ivana Milanović1, Željko GRAHEK1, 1Ruđer Bošković Institute..................................................................................................... 182
EVALUATION OF PHYSICO-CHEMICAL PROPERTIES AND BIODEGRADATION OF POLYMERIC MEMBRANES BASED CHITOSANA,
STARCH, AND POLYVINYLPYRROLIDONE (PVP) SYNTHESIZED BY GAMMA RADIATION AT DIFFERENT DOSES AND DOSE RATES
Jorge Gabriel dos Santos Batista1, Ana Carolina Moreira Fonseca2, Ademar Benévolo Lugão3, 1Instituto de Pesquisas Energéticas e Nucleares
(IPEN / CNEN - SP)......................................................................................................................................................................................................................... 183
EFFECT OF γ-IRRADIATION ON RADICAL SCAVENGING, REDUCING POWER AND LIPID PEROXIDATION INHIBITION PROPERTIES
OF HYDROALCOHOLIC EXTRACTS FROM MALVA NEGLECTA
José Virgílio Santulhão Pinela1-2, Amilcar L. Antonio1-3, Lillian Bouçada de Barros1, Ana M. Carvalho1, M. Beatriz P. P. Oliveira2, Isabel C. F.
R. Ferreira1, 1Centro de Investigação de Montanha (CIMO), ESA, Instituto Politécnico de Bragança, 2REQUIMTE/Departamento de Ciências Químicas,
Faculdade de Farmácia, Universidade do Porto, 3Centro de Ciências e Tecnologias Nucleares, IST, Universidade de Lisboa...................................................... 184
Analysis of phenolic compounds in Tropaeolum majus L. processed by ionizing radiation
Amanda Cristina Ramos Koike1-2, João C. M. Barreira2, Lillian Barros2, Celestino Santos-Buelga3, Anna Lucia C. H. Villavicencio1,
Isabel C. F. R. Ferreira2, 1Instituto de Pesquisas Energéticas e Nucleares (IPEN - CNEN/SP), 2Centro de Investigação de Montanha (CIMO), ESA, Instituto
Politécnico de Bragança, 3Grupo de Investigación en Polifenoles (GIP-USAL), Faculty of Pharmacy, University of Salamanca................................................. 185
Impact of gamma irradiation on chemical composition of Melissa officinalis L.
Eliana Pereira1-2, Amanda Cristina Ramos Koike3, Amilcar L. Antonio1-4, Lillian Barros1, Isabel C. F. R. Ferreira1, 1Mountain Research Centre
(CIMO), ESA, Polytechnic Institute of Bragança, 2GIP-USAL, Faculty of Pharmacy, University of Salamanca, 3Instituto de Pesquisas Energéticas e Nucleares
(IPEN/CNEN-SP), 4Centro de Ciências e Tecnologias Nucleares, IST, Universidade de Lisboa.................................................................................................... 186
INFLUENCE OF ANTIOXIDANT LOADING ON THE γ-EXPOSURE OF ETHYLENE-PROPYLENE TERPOLYMER
Heloísa Augusto Zen1, Traian Zaharescu2, Mariana Mădălina Marinescu2, Sandra Regina scagliusi1, Elizabeth Carvalho Leite Cardoso1,
Ademar Benevolo Lugão1, 1IPEN, Center of Chemistry and Environment, 2INCDIE ICPE CA, Department of Advanced Materials...................................... 187
THERMAL RESISTANCE OF EPDM/IIR SYSTEMS UNDER γ-IRRADIATION
Sandra Regina Scagliusi1, Traian Zaharescu2, Heloísa Augusto Zen1, Elizabeth Leite Carvalho Cardoso1, Silviu JIPA3, Ademar Benévolo Lugão1,
1
IPEN, Center of Chemistry and Environment, 2INCDIE ICPE CA, Department of Advanced Materials, 3University of Valachia, Faculty of Science and Arts...... 188
Radioecological and Geochemistry
RN-222 AND STABLE ISOTOPES AS A NATURAL TRACER IN GROUNDWATER-SURFACE WATER INTERACTIONS AT THE ARTIFICIAL
RECHARGE SYSTEM
Yoon Yeol Yoon1, Kil Yong Lee1, Soo Young Cho1, Kyu Chul Ha1, 1Geologic Environment Division, Korea Institute of Geoscience and Mineral Resources
(KIGAM).......................................................................................................................................................................................................................................... 191
THE CONTRIBUTION OF MINING ACTIVITIES ON ANTHROPOGENIC INPUT OF Cu, Pb AND Zn IN THE CANANÉIA-IGUAPE SYSTEM
Keila Modesto Tramonte1, Paulo Alves de Lima Ferreira1, Andreza Portella Ribeiro1-2, Rubens César Lopes Figueira1, Michel Michaelovitch
de Mahiques1, 1Instituto Oceanográfico da Universidade de São Paulo, 2Universidade Nove de Julho (UNINOVE), Mestrado de Gestão Ambiental e
Sustentabilidade................................................................................................................................................................................................................................ 192
SEDIMENTATION PROCESSES IN THE SEMI-ENCLOSED BAY DEDUCED FROM VERTICAL PROFILES OF 137Cs MASSIC ACTIVITIES
(KAŠTELA BAY, ADRIATIC SEA, CROATIA)
Ivanka Lovrenčić Mikelic1, Višnja OREŠČANIN2, Krunoslav ŠKARO3, Delko BARIŠIĆ1, 1Laboratory for Radioecology, Division for Marine and
Environmental Research, Ruđer Bošković Institute, 2Advanced Energy Ltd, 3Hydrographic Institute of the Republic of Croatia, Oceanographic Department........ 193
STATISCAL ANALISYS OF DISCREPANTS RADIOECOLOGICAL DATA USING MONTE CARLO BOOTSTRAP METHOD
Arykerne Nascimento Casado da Silva1, Romilton dos Santos Amaral1, José Wilson Vieira1, José Araújo dos Santos Júnior1, 1Nuclear Energy
Department of Federal University of Pernambuco........................................................................................................................................................................... 194
A 10-year record of seasonal variation of 7Be in particulate matter and plants of Cerrado biome, Brazil
Bruno Burini Robles Arine1, Marco Antonio Proença Vieira Moraes1, André Luis Lima de Araújo1, 1Centro Tecnológico da Marinha em São Paulo Laboratório Radioecológico.............................................................................................................................................................................................................. 195
21
Determination of Cesium Contamination in Marine Sediments from North of Gulf of Mexico
Miguel Angel Zúñiga Pérez1, Juan Manuel Navarrete Tejero1, Trinidad Martínez Castillo1, Samuel Tejeda Vega2, 1Facultad de Química, Edificio D,
Universidad Nacional Autónoma de México, 2Instituto Nacional de Investigaciones Nucleares, Gerencia de Ciencias Ambientales........................................... 196
Microbial effect on the aqueous uranium(VI) adsorption by bentonite under anaerobic condition
Seung Yeop Lee1, Ji Young Lee1, Min Hoon Baik1, Jong Tae Jeong1, Kyungsu S. Kim1, 1Korea Atomic Energy Research Institute (KAERI).................... 197
Radiological characterization of the varieties Burley and Virginia of Nicotiana tabacum L. cultivated in Brazil
Carolina Fernanda da Silva1, Sandra Regina Damatto1, Rique Jones Ferreira Xavier da Rocha1, Marcos Medrado de Alencar1, 1Instituto de Pesquisas
Energéticas e Nucleares (IPEN / CNEN - SP).................................................................................................................................................................................. 198
SEDIMENTATION RATES BY 210Pb METHOD AND TRACE ELEMENTS BY INAA IN TWO SEDIMENT CORES FROM THE TIETÊ RIVER,
SÃO PAULO, BRAZIL
Sandra Regina Damatto1, Flavio R. Rocha2, Daiane Baumgardt1, Lucas M. Castro2, Bruno Tappiz2, Paulo S. Cardoso da SILVA2, Deborah I. T.
FÁVARO2, 1Laboratório de Radiometria Ambiental - IPEN-CNEN-SP, 2 Laboratório de Análise por Ativação com Nêutrons, Centro do Reator de Pesquisas
(LAN/CRPq) - IPEN/CNEN-SP....................................................................................................................................................................................................... 199
Radiopharmaceutical Chemistry
RADIOTRACERS SORPTION STUDIES TO EVALUATE THE METAL REMOVAL POTENTIAL OF METAL-RESISTANT BACTERIAL
BIOFILM
Katia Noriko Suzuki1, Melissa Nogueira Sondermann1, Fatima P. Canesin1, Mirian Araujo Carlos Crapez2, Elisamara Sabadini-Santos1, Luis
F Bellido3, Edimar C. Machado4, Wilson Machado1, Ricardo Tadeu Lopes5, Alfredo Victor Bernedo Bellido1, 1Departamento de Geoquímica,
Universidade Federal Fluminense (UFF), 2Programa de Pós-Graduação em Biologia Marinha, Universidade Federal Fluminense (UFF), 3Instituto de
Radioproteção e Dosimetria (IRD/CNEN), 4Instituto Federal de Educação, Ciência e Tecnologia do Rio de Janeiro, 5Laboratório de Instrumentação Nuclear,
Universidade Federal do Rio de Janeiro........................................................................................................................................................................................... 203
Radiosensitizer effect of selenium in cells challenged with gamma radiation (60Cobalt)
Bárbara Abranches de Araujo Porto1, Luciana Mara Costa Moreira1, Frederico Haddad Ribeiro1, Luiz Cláudio Moura Belo1, Maria José Neves1,
1
Lab. Radiobiologia, CDTN/CNEN.................................................................................................................................................................................................. 204
Evaluation of anticancer activity of lanthanide gadolinium and its radioisotope 159Gd against malignant
glioblastoma
Izabela Galvão1, Raquel Gouvea dos Santos1, Maria José Neves1, 1Lab. Radiobiologia, CDTN/CNEN............................................................................ 205
THEORETICAL STUDY OF Re AND Tc DMSA COMPLEXES
Alejandro BLANCO-GONZÁLEZ1, Daniel HERNÁNDEZ-VALDÉS1, Zalua RODRÍGUEZ-RIERA1, Ulises Jaúregui-Haza1, Luis DUCAT-PAGES2, Luis
PIZARRO-LOU2, 1Instituto Superior de Tecnologías y Ciencias Aplicadas (InSTEC), 2Centro de Isótopos.................................................................................. 206
BIODISTRIBUTION OF 4,4’-DIFORMYL-1,6-DIPHENOXYHEXANE LABELED WITH IODINE-131
Nesibe Avcibasi1, Hande Efe1, Hasan Demiroğlu2, Gökçen Topal3, Uğur Avcıbaşı2, 1Ege University - Ege Higher Vocational School, 2Celal Bayar
University - Faculty of Arts and Science, Department of Chemistry, 3Celal Bayar University, Faculty of Medicine, Department of Nuclear Medicine.............. 207
INVESTIGATION OF THERAPEUTIC EFFICIENCY OF PHENYTOIN (PHT) LABELED WITH RADIOACTIVE 131I IN THE CANCER CELL
LINES
Cansu Uzaras1, Uğur Avcıbaşı1, Emin İlker Medine2, Ayfer Yurt Kilçar2, Zümrüt Biber Müftüler2, Hasan Demiroğlu1, Perihan Ünak2,
1
Celal Bayar University, Faculty of Arts and Science, Department of Chemistry, 2Ege University, Institute of Nuclear Sciences, Department of Nuclear
Applications...................................................................................................................................................................................................................................... 208
AUTOMATED PRODUCTION AND QUALITY TESTING OF 18F-LABELLED RADIOTRACERS USING THE BG75 SYSTEM
Atilio I. Anzellotti1, Aaron McFarland1, Jim BAILEY1, Doug Ferguson1, 1ABT Molecular Imaging Inc................................................................. 209
INFLUENCE OF GAMMA RADIATION ON THE RELEASE OF THE CONTROLLED DRUG POLYMER MATRIX
Jorge Gabriel dos Santos Batista1, Talita Aparecida de Moraes Vrechi1, Ademar Benévolo Lugão1, 1Instituto de Pesquisas Energéticas e Nucleares (IPEN
/ CNEN - SP).................................................................................................................................................................................................................................... 210
I AND 123I PURIFICATION FOR BIOMOLECULES LABELING
Marcela Forli Catanoso1, João Alberto Osso Jr.2, 1Hospital Israelita Albert Einstein, 2International Atomic Energy Agency (IAEA)....................................... 211
131
Radiation Protection
DIRECT METHOD FOR ASSESSEMENT OF AMINOPOLYETHER CONCENTRATIONS ON 18F-FDG SAMPLES
Renata Lins Carneiro Leão1, João Eudes do Nascimento1, Natalia Cassia do Espirito Santo Nascimento1, Mércia Liane de Oliveira1, 1Centro
Regional de Ciências Nucleares do Nordeste................................................................................................................................................................................... 215
OPTIMIZATION OF METHODOLOGY FOR THE DETERMINATION OF GROSS ALPHA AND BETA ACTIVITY IN WATER BY LSC
Ademar de Oliveira Ferreira1, Marcelo Bessa Nisti1, Cátia Heloisa Rosignoli Saueia1, Barbara MAZZILLI1, 1Laboratório de Radiometria Ambiental,
Instituto de Pesquisas Energéticas e Nucleares (IPEN).................................................................................................................................................................... 216
22
DETERMINATION OF THE RADIATION DOSE IN THE OPERATOR POSITION IN MAMMOGRAPHY EQUIPMENT
Jacqueline Sales Barreira1, Sarah Damasceno Pinheiro Huet1, Vitor Vivolo1, 1Instituto de Pesquisas Energéticas e Nucleares - IPEN/CNEN....... 217
DETERMINATION OF RADIATION DOSE IN SURFACE BREAST USING TWO TYPES OF PMMA SIMULATORS
Jacqueline Sales Barreira1, Sarah Damasceno Pinheiro Huet1, Vitor Vivolo1, 1Instituto de Pesquisas Energéticas e Nucleares - IPEN/CNEN............... 218
DOSIMETRIC EVALUATION OF INHOMOGENEITY EFFECTS IN THE SPINAL CORD
Andre Lima de Souza Castro1, Larissa Thompson1, Hugo Leonardo Lemos Silva2, Tarcísio Passos Ribeiro Campos1, 1Universidade Federal de Minas
Gerais, 2Santa Casa de Miserocórdia................................................................................................................................................................................................ 219
Evaluation of profenofos in aqueous solution by electrons beam
Flávio Thihara Rodrigues1, Eric Marchioni2, Sonia Lordel2, Florent Kuntz3, Anna Lucia Casañas Haasis Villavicencio1, Diane JulienDavid2, 1Instituto de Pesquisas Energéticas e Nucleares (IPEN-CNEN/SP), Centro de Tecnologia das Radiações, 2IPHC, UMR 7178, Equipe de Chimie
Analytique des Molécules BioActives-Université de Strasbourg, Faculté de Pharmacie, 3Aérial, Centre de Ressources Technologiques, Parc d’Innovation...... 220
MONITORING OF ENDS WORKERS EXPOSED POSITRON EMITTERS
Natalia Cassia do Espirito Santo Nascimento1, Êudice Correia Vilela1, Mércia Liane de Oliveira1, 1Centro Regional de Ciências Nucleares............ 221
GAMMA EXPOSURE DUE TO BUILDING MATERIALS IN A RESIDENTIAL BUILDING AT PERUÍBE, SÃO PAULO, BRAZIL
Camila Dias Cazula1, Marcia Pires de Campos1, Barbara P. MAZZILLI1, 1Instituto de Pesquisas Energéticas e Nucleares.................................................. 318
23
POSTER SESSION
2 - SEP 18 | Thursday
Nuclear and Radiochemistry
RADIOLABELLING OF NANOPARTICLES AND ITS USE FOR TRANSPORT STUDIES
Karsten Franke1, Stefan Schymura1, Heike Hildebrand1, Johannes Kulenkampff1, 1Dept. Reactive Transport, Institute of Resource Ecology,
Helmholtz-Zentrum Dresden-Rossendorf......................................................................................................................................................................................... 227
MUON SCIENCE: PROVIDING A FACTOR OF 36 IN H-ATOM ISOTOPIC MASS
Donald G. Fleming1, P. B. Bakule2, B. C. Garrett3, S. L. Mielke4, D. G. Thruhlar4, 1TRIUMF, Vancouver, BC, Canada 2Physics Institute,
Prague, Czech Republic, 3Pacific Northwest Nat. Lab, Richland, WA, USA, 4Dept. of Chemistry, Univ. of Minnesota, MN, USA.............................................. 228
A NEW METHOD FOR THE DETERMINATION OF 226Ra BY ALPHA SPECTROMETRY
Giovani Bergamini1, Maria Helena Tirollo Taddei1, Mychelle Munyck Linhares Rosa1, Marcelo Tarquínio Ferreira1, Luan Teixeira Vieira
Cheberle1, Sandra Maria Cheberle dos Santos1, Neide Aparecida Mariano2, Erika Coaglia Trindade Ramos2, 1Brazilian Nuclear Energy Commission
/ Poços de Caldas Laboratory (CNEN / LAPOC), 2Federal University of Alfenas (UNIFAL/MG), 8Federal University of Alfenas (UNIFAL/MG).................... 229
MODULATION OF ALBUMIN EXPRESSION OF PLASMA IN RATS INDUCED BY RADIATION
Celso Vieira de Lima1, Patrícia Falcão1, Tarcisio Passos Ribeiro de Campos1, 1Departamento de Ciências e Técnicas Nucleares, Engenharia Nucelar,
Universidade Federal de Minas Gerais (UFMG).............................................................................................................................................................................. 230
DETERMINATION OF 234U, 235U, 238U, 228Th, 230Th, 232Th, 226Ra, 228Ra, and 210Pb IN FOODS OF THE BRAZILIAN TOTAL DIET
Mychelle Munyck Linhares Rosa1-2, Maria Helena Tirollo Taddei1, Luan Teixeira Vieira Cheberle1, Marcelo Tarquinio Ferreira1, Sandra Maria
Cheberle Santos1, Roseane P. Avegliano2, Vera Akiko MAIHARA2, Giovani Bergamini, 1Laboratório de Poços de Caldas (CNEN/LAPOC), 2Instituto
de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP)................................................................................................................................................................ 231
SOIL-TO-PLANT TRANSFER FACTORS FOR RADIONUCLIDES IN SAMPLES OF LEMON BALM (MELISSA OFFICINALIS) COMMONLY
USED AS A MEDICINAL PLANT
Fábio Vitório Sussa1, Marcos Medrado de Alencar1, Barbara P. MAZZILLI1, Paulo S. Cardoso da SILVA1, 1Instituto de Pesquisas Energéticas e Nucleares
(IPEN – CNEN/SP).......................................................................................................................................................................................................................... 232
STANDARDIZATION OF 18F BY LIQUID SCINTILLATION SPECTROMETRY WITH THE CIEMAT/NIST 3H-STANDARD EFFICIENCY
TRACING METHOD
Maria da Conceição de Farias Fragoso1, Emerson Emiliano Gualberto de FARIAS2, Mércia L. de Oliveira1, Elvis Joacir de FRANÇA1, Eliane V.
Honorato1, Fernando Roberto de Andrade Lima1, 1Centro Regional de Ciências Nucleares do Nordeste - CRCN-NE -Comissão Nacional de Energia
Nuclear (CNEN)...................................................................................................................................................................................................................... 233
Nuclear and Related Techniques
SEMICONDUCTOR OXIDE EVALUATION OF MECHANICAL AND LASER MARKED ASTM F139 STAINLESS STEEL VIA HYPERFINE
INTERACTIONS AND MOTT-SCHOTTKY TECHNIQUES
Eurico Felix Pieretti1, Artur W. Carbonari1, Fabio H. M. Cavalcante1, Elisabete Jorge Pessine1, Olandir Vercino Correa1, Tomaz Puga
Leivas2, Maurício David Martins das Neves1, 1Instituto de Pesquisas Energéticas e Nucleares (IPEN-CNEN/SP), 2Instituto de Ortopedia e Traumatologia do
Hospital das Clínicas da Faculdade de Medicina da Universidade de São Paulo (IOT/HCFMUSP).............................................................................................. 237
ENHANCING NAA RESULTS BY USING ROBUST STATISTICS
Guilherme Soares Zahn1, Frederico Antonio Genezini1, Marcello Secco1, Regina Beck Ticianelli1, Ana Maria Graciano Figueiredo1, 1Instituto de
Pesquisas Energéticas e Nucleares – IPEN-CNEN/SP..................................................................................................................................................................... 238
INSTRUMENTAL NEUTRON ACTIVATION ANALYSIS OF KILOGRAM-SIZED SAMPLES OF DOG FOOD
Camila Elias1, Anneke Koster-Ammerlaan2, Elisabete A. De Nadai Fernandes1, Peter Bode3, Márcio Arruda Bacchi1, 1Centro de Energia
Nuclear na Agricultura (CENA), Universidade de São Paulo (USP), 2Human Resource Management, Delft University of Technology (TUDelft), 3Radiation
Science and Technology, Delft University of Technology (TUDelft).............................................................................................................................................. 239
ZINC MAPPING IN HUMAN PROSTATE SPHEROIDS USING X-RAY MICROFLUORESCENCE
Roberta Gama Leitão1, Carlos A. N. Santos2, Antonio Palumbo Jr3, Pedro A. V. R. Souza4, Catarine G. L. Canellas5, Marcelino José dos
Anjos6, Luiz E. NASCIUTTI7, Ricardo Tadeu Lopes8, 1Laboratório de Instrumentação Nuclear, (PEN / COPPE / UFRJ), 2Laboratório de Biotecnologia
(Bioengenharia / DIPRO / INMETRO), 3Laboratório de Interações Celulares (ICB / CCS / UFRJ), 4Serviço de Urologia, Hospital Federal do Andaraí, 5Serviço
de Urologia, Hospital Federal do Andaraí, 6Universidade do Estado do Rio de Janeiro, 7Instituto de Física (UERJ), 8COPPE/UFRJ........................................... 240
LEAD IN THE ENVIRONMENT OF THE METROPOLITAN ZONE OF THE TOLUCA VALLEY, IN MEXICO
Trinidad Martínez Castillo1, Graciela Zarazúa Ortega2, Alberto Fernández Alarcón1, Ciro Márquez Herrera1, Samuel Tejeda Vega2, Pedro
Ávila-Pérez2, Josefina Poblano-Bata3, 1Facultad de Química, Departamento de Química Inorgánica y Nuclear, Universidad Nacional Autónoma de
México, 2National Institute of Nuclear Research, 3Autonomous University of México State......................................................................................................... 241
24
RARE EARTH ELEMENT ASSESSMENT IN A SEDIMENTARY PROFILE FROM JURUMIRIM RESERVOIR, SÃO PAULO STATE, BRAZIL,
BY NAA AND ICP-MS
Sharlleny Alves Silva1, Robson Leocadio Franklin1, Déborah I. T. FÁVARO2, Wanilson Luiz-Silva3, 1Setor de Química Inorgânica - ELAI Companhia Ambiental do Estado de São Paulo, 2Laboratório de Análise por ativação Neutrônica - LAN-CRPq, Instituto de Pesquisas Energéticas e Nucleares
(IPEN/CNEN – SP), 3Departamento de Geologia e Recursos Naturais – DGRN, Instituto de Geociências................................................................................... 242
CHARACTERIZATION OF COMMERCIAL WHITE CLAYS
Giovanni Del Sordo FILHO1, Sônia Maria Barros de Oliveira2, Marcos A. Scapin1, Paulo S. Cardoso da SILVA1, 1Energy and Nuclear Research Institute
(Instituto de Pesquisas Energéticas e Nucleares), 2Institute of Geosciences, University of São Paulo............................................................................................ 243
PROVENANCE STUDIES IN AMAZON BASIN BY MEANS OF ELEMENTAL CHEMISTRY COMPOSITION OBTAINED BY INAA
José Osman dos Santos1, Casimiro Sepulveda MUNITA2, Emílio Alberto Amaral Soares3, 1Instituto Federal de Educação, Ciência e Tecnologia de Sergipe
(IFS), 2Instituto de Pesquisas Energéticas e Nucleares (IPEN–CNEN/SP), 3Universidade Federal do Amazonas, (UFAM).......................................................... 244
TRACKING IMPACTS ON CHEMICAL ELEMENT DISTRIBUTION IN DEEP SEDIMENT PROFILES FROM A RURAL AREA OF THE
PIRACICABA RIVER BASIN
Elvis Joacir de FRANÇA1, Elisabete A. De Nadai Fernandes2, Andrius Marcel Joventino do Carmo1, Vanessa S. Rodrigues1, Emerson Emiliano Gualberto
de FARIAS1, 1Divisão de Pesquisa e Desenvolvimento, Centro Regional de Ciências Nucleares do Nordeste, Comissão Nacional de Energia Nuclear,
2
Radioisotopes Laboratory, Centro de Energia Nuclear na Agricultura, Universidade de São Paulo.............................................................................................. 245
NEUTRON ACTIVATED RUTHENIUM(II) COMPLEXES FOR USE IN GLIOBLASTOMA THERAPY
Aline Monezi Montel1, Raquel Gouvêa dos Santos2, Elisângela de Paula Silveira-Lacerda3, Alzir Azevedo Batista4, Wagner Gouvêa dos
Santos1, 1Laboratório de Genética, Regional Jataí, Universidade Federal de Goiás – UFG, 2Centro Nacional de Desenvolvimento da Tecnologia Nuclear,
CDTN, 3Laboratório de Genética Molecular e Citogenética, Instituto de Ciências Biológicas, Universidade Federal de Goiás - UFG, 4Departamento de Química,
Universidade Federal de São Carlos ................................................................................................................................................................................................ 246
ENVIRONMENTAL QUALITY OF RIPARIAN SOILS FROM THE PIRACICABA RIVER BASIN
Elvis Joacir de FRANÇA1, Elisabete A. De Nadai Fernandes2, Jônas Henrique Alves de Souza1, Paulo Correia da Silva Neto1, Rebeca da Silva
Cantinha1, 1Divisão de Pesquisa e Desenvolvimento, Centro Regional de Ciências Nucleares do Nordeste, Comissão Nacional de Energia Nuclear,
2
Radioisotopes Laboratory, Centro de Energia Nuclear na Agricultura, Universidade de São Paulo.............................................................................................. 247
EVALUATION OF VEGETATION CHEMICAL ELEMENT COMPOSITION APPLIED TO ENVIRONMENTAL MONITORING OF URBAN
RIPARIAN AREAS
Elvis Joacir De FRANÇA1, Elisabete A. De Nadai Fernandes2, Evely Elen de SOUSA1, Paulo Correia da Silva Neto1, Rebeca da Silva Cantinha1,
1
Divisão de Pesquisa e Desenvolvimento, Centro Regional de Ciências Nucleares do Nordeste, Comissão Nacional de Energia Nuclear, 2Radioisotopes
Laboratory, Centro de Energia Nuclear na Agricultura, Universidade de São Paulo....................................................................................................................... 248
USE OF ROBUSTS MEANS ON THE DETERMINATION OF URANIUM FISSION INTERFERENCE FACTOR AND ANALYSIS OF CERFIEDE
REFERENCE MATERIALS
Iberê Souza Ribeiro Júnior1, Frederico Antonio Genezini1, Mitiko Saiki1, Guilherme Soares Zahn1, 1Instituto de Pesquisas Energéticas e Nucleares
(IPEN-CNEN/SP)............................................................................................................................................................................................................................. 249
REFERENCE VALUES FOR ENVIRONMENTAL QUALITY EVALUATION STUDIES USING INVERTEBRATES. 1.ESTAÇÃO ECOLÓGICA
DOS CAETETUS
Marcelo da Rocha Leão de Magalhães1, Elvis Joacir de FRANÇA1, Elisabete A. De Nadai Fernandes2, Felipe Yamada Fonseca1, 1Divisão de
Pesquisa e Desenvolvimento, Centro Regional de Ciências Nucleares do Nordeste, Comissão Nacional de Energia Nuclear, 2Radioisotopes Laboratory, Centro
de Energia Nuclear na Agricultura, Universidade de São Paulo...................................................................................................................................................... 250
ARSENIC IN INVERTEBRATE SPECIES FROM THE PIRACICABA RIVER BASIN
Marcelo da Rocha Leão de Magalhães1, Elvis Joacir de FRANÇA1, Elisabete A. De Nadai Fernandes2, Felipe Yamada Fonseca1, 1Divisão de
Pesquisa e Desenvolvimento, Centro Regional de Ciências Nucleares do Nordeste, Comissão Nacional de Energia Nuclear, 2Radioisotopes Laboratory, Centro
de Energia Nuclear na Agricultura, Universidade de São Paulo...................................................................................................................................................... 251
NATURAL RADIONUCLIDES IN MANGROVE SOILS FROM THE PERNAMBUCO STATE, BRAZIL
Jose Daniel Soares de PAIVA1, Evely Elen Sousa1, Marcelo da Rocha Leão de Magalhães1, Emerson Emiliano Gualberto de FARIAS1, Andrius Marcel
Joventino do Carmo1, Elvis Joacir de França1, 1Divisão de Pesquisa e Desenvolvimento, Centro Regional de Ciências Nucleares do Nordeste, Comissão
Nacional de Energia Nuclear............................................................................................................................................................................................................ 252
ACCUMULATION OF TOXIC CHEMICAL ELEMENTS IN TERRESTRIAL MOLLUSKS
Julyanne Torres Bezerra de Mélo1, Rebeca da Silva Cantinha1, Ana Maria Mendonça de Albquerque Melo2, Marcelo da Rocha Leão de Magalhães1,
Emerson Emiliano Gualberto de FARIAS1, Alesxandro F. Nascimento1, Elvis Joacir de FRANÇA1, 1Divisão de Pesquisa e Desenvolvimento –
DIPED, Centro Regional de Ciências Nucleares do Nordeste – CRCN/NE, Comissão Nacional de Energia Nuclear – CNEN, 2Departamento de Biofísica e
Radiobiologia, Universidade Federal de Pernambuco...................................................................................................................................................................... 253
MONTE CARLO ASSISTED EFFICIENCY CURVE FOR THE DETERMINATION OF RADIONUCLIDES IN BIOLOGICAL MATERIAL
José Daniel Soares de Paiva1, Evely Elen Sousa1, Marcelo da Rocha Leão de Magalhães1, Emerson Emiliano Gualberto de FARIAS1, Andrius Marcel
Joventino do Carmo1, Elvis Joacir de França1, 1Divisão de Pesquisa e Desenvolvimento, Centro Regional de Ciências Nucleares do Nordeste, Comissão
Nacional de Energia Nuclear............................................................................................................................................................................................................ 254
INSTRUMENTAL NEUTRON ACTIVATION ANALYSIS TO DETERMINE THE ANNUAL RADIATION DOSE FOR THERMOLUMINESCENCE
DATING OF POTTERY FROM CANINDÉ-SERGIPE, BRAZIL
José Osman dos Santos1, Mauro José dos Santos1, Casimiro Sepulveda Munita2, 1Instituto Federal de Educação, Ciência e Tecnologia de Sergipe, IFS,
2
Instituto de Pesquisas Energéticas e Nucleares (IPEN–CNEN/SP)................................................................................................................................................ 255
25
SILICON IN TEN SUGARCANE VARIETIES MEASURED BY ENERGY DISPERSIVE X-RAY FLUORESCENCE
Maria Isabel Vega Martínez1, Cláudio Luís Gonzaga1, Elisabete A. De Nadai Fernandes1, Márcio Arruda Bacchi1, Lilian Seiko Kato1, Isabel
Cristina Azevedo Schiavinato1, Eduardo de Almeida1, 1Nuclear Energy Center for Agriculture (CENA), University of São Paulo (USP)....................... 256
Chemical characterization of brazilian beans using neutron activation analysis
Lilian Seiko Kato1, Elisabete A. De Nadai Fernandes1, Márcio Arruda Bacchi1, Gabriel Adrián Sarriés2, 1Nuclear Energy Center for Agriculture,
University of São Paulo (CENA/USP), 2College of Agriculture “Luiz de Queiroz”, University of São Paulo (ESALQ/USP)...................................................... 257
HEAVY METALS MEASUREMENT IN SANDY BEACHES: INFLUENCE OF THE BENTHIC FAUNA ASSOCIATED
Rodholfo Maciel de Mendonça Ribeiro1, Leonardo Q. Yokoyama1, Renata F. Barbosa1, Edgar Francisco Oliveira de Jesus2, Roberta de Oliveira
Resende Ribeiro3, Roseli Fernandes Gennari4, 1Department of Marine Sciences - UNIFESP, 2Nuclear Instrumentation Laboratory - UFRJ, 3Laboratory of
Chemical Control - UFF, 4Physics Institute, Sao Paulo University - USP........................................................................................................................................ 258
CONTRIBUTION TO FOOD SAFETY ASSURANCE OF THE FISH CONSUMED IN SÃO PAULO CITY: THE DETERMINATION OF
ELEMENTS BY NEUTRON ACTIVATION ANALYSIS
Karen Campos Fabiano1, Edson Gonçalves MOREIRA1, Marina Beatriz Agostini Vasconcellos1, 1Instituto de Pesquisas Energéticas e Nucleares, IPEN
– CNEN/SP....................................................................................................................................................................................................................................... 259
TRACE ELEMENTS DETERMINATION IN LEAVES OF NERIUM OLEANDER USING X-RAY FLUORESCENCE
Ramon Silva dos Santos1, Francis Anna Cardoso Reis de Almeida Sanches1, Arthur O. P. Neves1, Davi Ferreira de Oliveira1, Luis Fernando de
Oliveira1, Marcelino José dos Anjos1, 1Physics Institute, State University of Rio de Janeiro................................................................................................. 260
ANALYSIS OF TRACE ELEMENT IN RIVER WATER SURFACE USING A PORTABLE TOTAL REFLECTION X-RAY FLUORESCENCE
SYSTEM
Ana Cristina Moraes da Costa1, Ubiratan Barbosa de Araújo1, Edgar Francisco Oliveira de Jesus1, Marcelino José dos Anjos1-2, Ricardo Tadeu Lopes1,
1
Nuclear Instrumentation Laboratory – COPPE/UFRJ, 2State University of Rio de Janeiro, Physics Institute............................................................................... 261
RARE EARTH ELEMENTS: PAST, PRESENT AND FUTURE AT RADIOISOTOPES LABORATORY
Luís Gustavo Cofani dos Santos1, Elisabete A. De Nadai Fernandes1, Simone Silveira Nery da Silva Cofani dos Santos1, Márcio Arruda Bacchi1,
Gabriel Adrián Sarriés2, Mateus Eugênio Boscaro1, 1Centro de Energia Nuclear na Agricultura, Universidade de São Paulo, 2Escola Superior de
Agricultura Luiz de Queiroz, Universidade de São Paulo................................................................................................................................................................ 262
CHEMICAL CHARACTERIZATION OF MILK POWDER FOR THE PRODUCTION OF CERTIFIED REFERENCE MATERIAL
Simone Silveira Nery da Silva Cofani dos Santos1, Elisabete A. De Nadai Fernandes1, Luís Gustavo Cofani dos Santos1, Márcio Arruda Bacchi1,
Gabriel Adrián Sarriés2, 1Centro de Energia Nuclear na Agricultura, Universidade de São Paulo, 2Escola Superior de Agricultura Luiz de Queiroz,
Universidade de São Paulo............................................................................................................................................................................................................... 263
STUDIES ON RARE EARTHS IN URANIUM MINING WASTE ROCKS USING NEUTRON ACTIVATION ANALYSIS
Elisabete A. De Nadai Fernandes1, Márcio Arruda Bacchi1, Gabriel Adrián Sarriés2, Luís Gustavo Cofani dos Santos1, Mateus Eugenio Boscaro1,
Luiza Oide Wiikmann1, Peter Bode3, 1Centro de Energia Nuclear na Agricultura (CENA), Universidade de São Paulo (USP), 2Escola Superior de Agricultura
Luiz de Queiroz (ESALQ), Universidade de São Paulo (USP), 3Radiation Science and Technology, Delft University of Technology (TUDelft).............................. 264
Nuclear Reactors
OBTAINING OF THE NUCLEAR GRADE ZIRCONIUM TETRACHLORIDE BY THE CHLORINATION PROCESS
Rubens Chiba1, Eliene G. R. Menezes1, Marco Andreoli1, Emília Satoshi Miyamaru Seo1, 1IPEN - Instituto de Pesquisas Energéticas e Nucleares.... 267
Radioanalytical Chemistry
DEEP-SEA MICROSPHERULES FROM THE PACIFIC AND THE INDIAN OCEANS: ELEMENTAL COMPOSITION AND POSSIBLE ORIGIN
Zdeněk Řanda1, Jiří Mizera1, 1Nuclear Physics Institute, Academy of Sciences of the Czech Republic................................................................................. 271
MONITORING OF 226Ra, 228Ra, 210Pb AND 210Po IN THE COASTAL REGION OF SÃO PAULO STATE, BRAZIL, USING OYSTER Crassostrea
brasiliana
Gabriela de Jesus Lustoza Costa1, Cátia Heloisa Rosignoli Saueia1, Barbara P. Mazzilli1, Marilia Gabriela Miranda Catharino Semmler1,
Eduinetty Ceci Pereira Moreira de Sousa2, 1Instituto de Pesquisas Energéticas e Nucleares (IPEN), 2Instituto Oceanográfico da Universidade de São Paulo
(IO-USP)................................................................................................................................................................................................................................. 272
NITROGEN ASSAY BY INSTRUMENTAL PHOTON ACTIVATION ANALYSIS WITH THE MT-25 MICROTRON
Ivana Krausová1, Jiří Mizera1, Zdeněk Řanda1, Pavel Dostálek2, Jan Táborský3, Marcela Mádlíková1-3, Oldřich Faměra3, David
Chvátil1, Pavel Krist1, 1Nuclear Physics Institute, Academy of Sciences of the Czech Republic, 2Institute of Chemical Technology Prague, 3Czech
University of Life Sciences Prague................................................................................................................................................................................................... 273
URANIUM ISOTOPIC RATIO DETERMINATION BY ICP-MS
Luís Cláudio de OLiveira1, Israel Elias Ferraz1, Talita Sousa1, Ricardo Gonçalves Gomide1, Ieda de Souza Silva1, 1CTMSP – Centro Tecnológico da
Marinha em São. Iperó/SP................................................................................................................................................................................................................ 274
STUDY OF COMMERCIAL CHEMICAL ADDITIVES FOR CEMENTATION OF RADIOACTIVE WASTE GENERATED IN PRESSURIZED
WATER REACTOR
Vanessa Mota Vieira1, Clédola Cássia Oliveira de Tello1, 1Centro de Desenvolvimento da Tecnologia Nuclear (CDTN / CNEN)....................................... 275
26
Rapid determination of radiostrontium in groundwater using automated radionuclide separation system
Hyuncheol Kim1, Kun Ho Chung1, Yoonhee Jung1-2, Geun-Sik Choi1, Mun Ja Kang1, 1Environmental Radioactivity Assessment Team, Korea Atomic
Energy Research Institute, 2Korea University of Science and Technology...................................................................................................................................... 276
APPLICATION OF INSTRUMENTAL NEUTRON ACTIVATION ANALYSIS ON ICE CORE SAMPLES
Giovanni Baccolo1-2-3, Massimiliano Clemenza3-4, Barbara Delmonte2, Niccolò Maffezzoli3-4, Valter Maggi2, Ezio Previtali3-4, 1University
of Siena, 2Environmental Sciences Department, University of Milano-Bicocca, 3INFN section of Milano-Bicocca, 4Physics Department, University of MilanoBicocca.............................................................................................................................................................................................................................................. 277
Ca2+, Mg2+, Ba2+ End 226Ra, in Scales Formed in Pipes from Industrial Boilers
Claudia Miriam Braga Poggi1-2, Emerson Emiliano Gualberto de FARIAS1-2, Patrícia B. Silveira1, Crescêncio Andrade Silva Filho1, Elvis Joacir
de FRANÇA1, Maria Helena Paranhus Gazineu3, Clovis A. Hazin1, 1Centro Regional de Ciências Nucleares do Nordeste/Universidade Federal de
Pernambuco, 2Universidade Federal de Pernambuco, 3Universidade Católica de Pernambuco....................................................................................................... 278
DETERMINATION 238U AND 232Th IN MINERAL SANDS BY ALPHA SPECTROMETRY
Emerson Emiliano Gualberto De Farias1, Elvis Joacir De França1, Eliane Valentim Honorato1, Clovis A. Hazin1, 1Centro Regional De Ciências
Nucleares Do Nordeste - CRCN-NE/CNEN-PE.............................................................................................................................................................................. 279
MOUNTING AND CALIBRATION OF A SCINTILLATION SYSTEM FOR ENVIRONMENTAL RADON DETERMINATION
Emerson Emiliano Gualberto De Farias1, Elvis Joacir de França1, Clovis A. Hazin1, 1Centro Regional de Ciências Nucleares do Nordeste - CRCN-NE/
CNEN-PE.......................................................................................................................................................................................................................................... 280
Radiation Chemistry
A comparison of chemical dosimeters of reactor radiation for the assessment of contributions of neutron
and gamma radiation to the total dose
Bohumil Bartoníček1, Jan Kučera2, Ingrid Pytelová1, Romana Svitáková3, Jiri Horsky3, Martin Cabalka1, 1ÚJV Řež, a. s. 2Nuclear
Physics Institute ASCR, 3Institute of macromolecular Chemistry ASCR........................................................................................................................................ 283
EFFECTS OF IONIZING RADIATION ON THE PHYSICOCHEMICAL PROPERTIES OF RED WINE CABERNET SAUVIGNON
Fellipe Souza da Silva1, Anderson R. L. SANTOS1, Octavio MACEDO1, Walsan W. PEREIRA1, 1Instituto de Radioproteção e Dosimetria IRD/CNEN........ 284
226
Ra, 228Ra AND 40K IN SCALES FROM BOILERS OF INDUSTRIAL INSTALLATIONS
Claudia Miriam Braga Poggi1-2, Emerson Emiliano Gualberto de Farias1-2, Patrícia B. Silveira1, Crescêncio Andrade Silva Filho1, Elvis Joacir
de França1, Maria Helena Paranhus Gazineu3, Clovis A. Hazin1, 1Centro Regional de Ciências Nucleares do Nordeste, 2Universidade Federal de
Pernambuco, 3Universidade Católica de Pernambuco...................................................................................................................................................................... 285
IRRADIATION PROCESS APPLIED IN FISH SCALES: AN IMPROVEMENT OF ITS CAPACITY FOR METALLIC SORPTION?
Renata Bazante-Yamaguishi1, Áurea Beatriz Cerqueira Geraldo1, Eduardo Moura1, 1Nuclear and Energy Research Institute (Instituto de Pesquisas
Energéticas e Nucleares) - IPEN-CNEN-SP..................................................................................................................................................................................... 286
STUDY OF HYDROPHILIC MATERIALS AS TISSUE EQUIVALENT PHANTOMS FOR POSITRON EMISSION TOMOGRAPHY
M. Alkhorayef1, 1Department of Radiological Sciences, College of Applied Medical Sciences, King Saud University........................................................ 287
EPR Investigation of Butylated Hydroxytoluene and Estimated Uncertainty Associated with Different
Measurements
M Alkhorayef1-2, A. Mansour3-4, 1Department of Radiological Sciences, College of Applied Medical Sciences, King Saud University, 2Centre for
Nuclear and Radiation Physics, Department of Physics, University of Surrey, 3National Center for Radiation Research and Technology, Atomic Energy
Authority, 4INAYA Medical Collage Riyadh.................................................................................................................................................................................... 288
IONIZING RADIATION INFLUENCE IN LOW DENSITY POLYETHYLENE WITH CHARCOAL BLACK PIGMENT
Leonardo Gondim de Andrade E Silva1, Maurício César Ferreira Santos2, 1Instituto de Pesquisas Energéticas E Nucleares, Ipen-Cnen/Sp..................... 289
Radioecological and Geochemistry
SEDIMENTS FROM THE NORTH COAST OF THE GULF OF MEXICO: GEOCHEMICAL CHARACTERIZATION AND FRACTIONING
Brenda Beatriz Estañol Díaz1, Trinidad Martínez Castillo1, Miguel Ángel Zúñiga Pérez1, Samuel Tejeda Vega2, Graciela Zarazúa Ortega2, Juan
Manuel Navarrete Tejero1, 1Departamento de Química Inorgánica y Nuclear, Facultad de Química, Universidad Nacional Autónoma de México, 2National
Institute of Nuclear Research............................................................................................................................................................................................................ 293
Estimation of 220Rn efective dose in México
Trinidad Martínez Castillo1, Pedro GONZALEZ2, Alejandro Ramírez Chávez1, Omar Yahir MORALES1, Juan Manuel Navarrete Tejero1, 1Facultad de
Química, Departamento de Química Inorgánica y Nuclear, Universidad Nacional Autónoma de México, 2National Institute of Nuclear Research..................... 294
SEQUENTIAL EXTRACTION APPLIED TO PERUIBE BLACK MUD
Jefferson Koyaishi Torrecilha1, Marycel Elena Barboza Cotrim1, Paulo S. Cardoso da SILVA1, 1Instituto de Pesquisas Energéticas e Nucleares IPEN CNEN/SP.......................................................................................................................................................................................................................................... 295
27
SOIL CONTAMINATION OF PROCESS LIQUID FROM THE INDUSTRIAL PRODUCTION OF AMMONIUM DIURANATE
Hector Hugo Silva Medrado1, Nichele Cristina de Freitas Juchneski1, Ricardo A. QUEIROZ1, Tatiane P. AMORIM1, Wanderson S. ARAÚJO1, Renata R.
CARVALHO1, Pedro L. S. DIAS1, 1Indústrias Nucleares do Brasil................................................................................................................................................. 296
ACTIVATION ANALYSIS IN GEOCHEMICAL CHARACTERIZATION OF SEDIMENTS RELATED TO THE RIES IMPACT CRATER
Zdeněk Řanda1, Jiří Mizera1, Karel ŽÁK2, Roman Skála2, Jan Kameník1, 1Nuclear Physics Institute, Academy of Sciences of the Czech Republic,
2
Institute of Geology, Academy of Sciences of the Czech Republic................................................................................................................................................ 297
Geographical discrimination of Brazilian stingless bees by instrumental neutron activation analysis
André Luis Lima de Araújo1, Elisabete A. De Nadai Fernandes1, Márcio Arruda Bacchi1, Gabriel Ádrian Sarriés1, Andrés Enrique Lai Reyes1,
1
Nuclear Energy Center for Agriculture, University of São Paulo................................................................................................................................................... 298
Study of 222Rn, 226Ra and 238U concentration in samples from groundwater aquifer belonging to the Osamu
Utsumi mine, UTM / Caldas-MG
Heber Luiz Caponi Alberti1, Nivaldo Carlos da Silva1, Peter Marshal Fleming2, Sueli Yoshinaga Pereira3, Flavio Henrique de Souza Moreira4,
1
Comissão Nacional de Energia Nuclear (LAPOC / CNEN), 2Comissão Nacional de Energia Nuclear (CDTN/ CNEN), 3Universidade Estadual de Campinas ,
4
Universidade Federal de Alfenas..................................................................................................................................................................................................... 299
A comparative study using Alfa-Guard and liquid scintilation counting to determine 222Rn in spring water in
Poços de Caldas-Brazil
Flávio Henrique de Souza Moreira1-2, Heber Luiz Caponi Alberti2, Maria Helena Tirollo Taddei2, Nivaldo C. Silva2, Peter Marshall
Fleming3, 1Universidade Federal de Alfenas – Campus Poços de Caldas, 2Comissão Nacional de Energia Nuclear (LAPOC/CNEN), 3Comissão Nacional de
Energia Nuclear (CDTN/CNEN)...................................................................................................................................................................................................... 300
Gamma-ray emitter radionuclides in soils from an institute of technology campus in São Paulo city
Santiago Scarcelli Santos1, Marcelo Francis Máduar2, Pedro Miranda Junior1, 1Instituto Federal de Educação, Ciência e Tecnologia de São Paulo
(IFSP), 2Instituto de Pesquisas Energéticas e Nucleares (IPEN-CNEN/SP).................................................................................................................................... 301
Radiopharmaceutical Chemistry
RADIOLABELED THERMORESPONSIVE POLYMERS FOR LOCAL THERAPY
Veronika Felklová1, Martin Hrubý1, Jan Kučka1, Pavla Jendelová2, Pavla Poučková3, 1Institute of Macromolecular Chemistry, Czech Academy
of Science, v.v.i., 2Institute of Experimental Medicine, Academy of Science of the Czech republic, v.v.i, 3Institute of Biophysics and Informatics, First Faculty
of Medicine, Charles University in Prague....................................................................................................................................................................................... 305
STANDARDIZATION OF 153Sm BY COUNTING ANTICOINCIDENCE LIVE-TIMED AND EXTENDIBLE DEAD-TIME
Adilson da Silva Laranjeira1, Carlos José da Silva1, José Ubiratan Delgado1, Paulo Alberto Lima da CRUZ1, Roberto POLEDNA1, Ronaldo L. da
Silva1, Antônio Eduardo de Oliveira1, 1Instituto de Radioproteção e Dosimetria/Comissão Nacional de Energia Nuclear (IRD/CNEN).............................. 306
Hf as a competitor in the synthesis of 177Lu-DOTATATE
José de Souza Caldeira Filho1, 1Centro de Tecnologia das Radiações. Instituto de Pesquisas Energéticas e Nucleares - IPEN/CNEN/SP.......................... 307
RADIOSYNTHESIS OF CHOLINE LABELLED WITH CARBON-11 AND PRELIMINARY IMAGING STUDY IN TUMOR MODEL
Marina Bicalho Silveira1, Bruno Melo Mendes1, Danielle Cunha Campos1, Adriana Márcia Guimarães Rocha1, Soraya Maria Zandim Maciel Dias
Ferreira1, Juliana Batista da Silva1, 1Unidade de Pesquisa e Produção de Radiofármacos (UPPR) - Centro de Desenvolvimento da Tecnologia Nuclear
(CDTN/ CNEN)................................................................................................................................................................................................................................ 308
EFFECT OF ELUENT COMPOSITION ON FINAL STEP OF [18F]FLUOROTHYMIDINE PRODUCTION AND ITS EFFECTIVENESS IN VITRO
Leonardo Tafas Constantino do Nascimento1, Marina Bicalho Silveira1, Soraya Maria Zandim Ferreira1, Raquel Gouvea dos Santos1, Juliana
Batista da Silva1, 1Unidade de Pesquisa e Produção de Radiofármacos - Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/ CNEN)....................... 309
Determination of gamma emitting radionuclidic impurities of 99Mo produced by nuclear fission of 235U
Daphne de Souza Said1, Carla Roberta de Barros Rodrigues Dias1, Josiane Zini1, Tânia de Paula Brambilla1, João Alberto Osso Junior1, 1Centro de
Radiofarmácia, Instituto de Pesquisas Energéticas e Nucleares (IPEN-CNEN/SP)......................................................................................................................... 310
INFLUENCE OF HUMIDITY IN THE 99mTc-ECD RADIOCHEMICAL PURITY
Elaine Vasconcelos dos Santos1, Mércia Liane de Oliveira1, Joao Eudes do Nascimento1, 1Centro Regional de Ciências Nucleares do Nordeste –
CRCN/CNEN.................................................................................................................................................................................................................................... 311
SYNTHESIS OF A NOVEL RADIOGALLIUM-PEPTIDE BASED ON DISINTEGRIN LEUC-B FOR TUMOR TARGETING
Lucilene Marcia Gabriel1, Anayive Perez-Rebolledo1, Daniel M Santos2, Adriano Monteiro de Castro Pimenta2, Felipe Henrique de Souza
Silva1, Eladio F. Sanchez3, Raquel Gouvea dos Santos1-4, 1Unit of Radiobiology, Center for Development of Nuclear Technology CDTN/CNEN,
2
Federal University of Minas Gerais, 3Ezequiel Dias Foundation, 4INCT- Molecular Medicine..................................................................................................... 312
Radiation Protection
CESIUM-137 CONTENT IN MILK - MONITORING AFTER FUKUSHIMA NUCLEAR POWER PLANT ACCIDENT
Flavia Groppi1, Simone Manenti1, Mauro L. Bonardi1, Luigi Gini1, Alexandra Ioannidou2, 1Università degli Studi di Milano & INFN, Physics Department –
LASA Laboratory, 2Aristotele University, Physics Department....................................................................................................................................................... 315
28
COMPARISON BETWEEN LM-OSL AND CW-OSL APPLIED TO IONIZING RADIATION DOSIMETRY
René Rojas Rocca1, Sonia Hatsue Tatumi1, 1Sao Paulo Federal University UNIFESP............................................................................................................. 316
A FEMALE VOXEL PHANTOM FOR RADIOPHARMACEUTICALS INTERNAL DOSIMETRY
Bruno Melo Mendes1-2, Iassudara Garcia de Almeida2, Bruno Machado Trindade2, Tarcísio Passos Ribeiro de Campos2, 1Centro de desenvolvimento
da Tecnologia Nuclear – CDTN/CNEN – Campus UFMG, 2Universidade Federal de Minas Gerais – UFMG, Departamento de Engenharia Nuclear - NRI –
Campus UFMG................................................................................................................................................................................................................................. 317
Estimation of Radiation Risks to Patients and occupational exposure in Pacemaker Interventional
Procedures
Khalid S. Alzimami1, Islam Hassan2, Abdelmoneim Sulieman3, 1Radiological Sciences Department, College of Applied Medical Sciences, King Saud
University, 2Salman bin Abdulaziz University, College of Applied Medical Sciences, Radiology and Medical Imaging Department 3Basic Science Department,
College of Medical Radiologic Sciences, Sudan University of Science and Technology........................................................................................................................ 319
BACKWARD DOSIMETRY USING GREEN QUARTZ AND A FEW VARIETY OF SILICATE MINERALS
Shigueo Watanabe1, Nilo Francisco Cano Mamani2, Renata de Faria Barbosa2, T. K. Gundu Rao1, 1Institute of Phyics, University of São Paulo,
2
Federal University of São Paulo...................................................................................................................................................................................................... 320
MONITORING OF ENDS WORKERS EXPOSED POSITRON EMITTERS
Natalia Cassia do Espirito Santo Nascimento1, Êudice Correia Vilela1, Mércia Liane de Oliveira1, 1Centro Regional de Ciências Nucleares do
Nordeste............................................................................................................................................................................................................................................ 321
Nuclear and Related Techniques
BIOMONITORING OF ESSENTIAL CHEMICAL ELEMENTS USING TERRESTRIAL MOLLUSKS L. ANGULIFERA OF PERNAMBUCO
MANGROVES
Julyanne T. B. MÉLO1, Rebeca S. CANTINHA1, Ana M. M. A. MELO2, Marcelo R. L. MAGALHÃES1, 1Divisão de Pesquisa e Desenvolvimento –
DIPED, Centro Regional de Ciências Nucleares do Nordeste – CRCN/NE, Comissão Nacional de Energia Nuclear – CNEN, 2Departamento de Biofísica e
Radiobiologia, Universidade Federal de Pernambuco...................................................................................................................................................................... 325
29
Invited Speakers
4th-INCC 2014 I 4th International Nuclear Chemistry Congress
Managing NAA in the Multi-Purpose OPAL Research Reactor Opportunities and Challenges
John W. Bennett1
1
Australian Nuclear Science and Technology Organisation (ANSTO), Lucas Heights, Australia, [email protected]
Australia’s OPAL research reactor is performing at a very high level of productivity, availability and
safety. It is a multi-purpose facility that serves a diverse range of key national and international stakeholder
communities including nuclear medicine, university researchers and industry. The demands on the irradiation
locations and neutron beam line instruments need to be carefully managed to optimise the utilization of the
reactor, maximize customer satisfaction and ensure the safety of personnel and facilities.
OPAL operates at a nominal 20 MW, producing high neutron fluxes in the heavy-water reflector vessel. The
neutron flux in the outer regions of the reflector vessel ranges from 1012 to 1013 cm-2 s-1 and is very highly
thermalized. These conditions have been found to be suitable for NAA and DNAA. Due to the very low
epithermal neutron component, the k0-method of standardization has been successfully adopted for routine
NAA. The OPAL facilities provide excellent opportunities for performing NAA reliably and accurately
for researchers in a wide range of academic disciplines, for primary and manufacturing industries, and for
metrology. On the other hand, the high flux and degree of thermalization means that the pneumatic irradiation
facilities are unsuitable for epithermal or fast NAA, since detailed neutronic and thermo-hydraulic safety
calculations have shown that the required cadmium shielding would melt. The paper will discuss in more
detail the opportunities and challenges for NAA in a high-powered reactor with a well-thermalized flux,
highlighting the need for access to sophisticated calculational tools and nuclear data.
A feature of a multi-purpose reactor is the large number of facilities that penetrate the reflector vessel. In
OPAL these include pneumatic irradiation facilities, rotating facilities for silicon doping, irradiation rigs for
Mo-99 production, multiple beam ports and a cold neutron source. The presence of these voids, cavities and
re-entrant tubes have an effect on the neutron flux and energy spectrum distribution throughout the reflector
vessel. It is recommended that detailed Monte Carlo modelling should be performed during the design
phase of a reactor to assess capabilities and limitations, so that there are no surprises during commissioning.
A further practical issue for managing NAA in this environment is that careful attention must be paid to
the scheduling of operations in the reactor during any planned period of NAA irradiation. For example,
NAA irradiations should be avoided in locations near any scheduled insertion or removal of uranium plates
for Mo-99 production because those actions may significantly change the neutron flux. In the event of
competing activities, high-value commercial operations can reasonably be expected to take priority over
lower value irradiations.
The paper will describe practical aspects of operating a successful NAA group in a highly regulated
organization. These include authorization requirements for NAA staff, the quality system, the safety process
for obtaining permission to irradiate any new type of sample, and the role of reactor utilization staff.
33
4th International Nuclear Chemistry Congress I 4th-INCC 2014
International Atomic Energy Agency (IAEA) programs in the area
of Radiopharmaceuticals
Uday Bhonsle1
Radiopharmaceutical Scientist, Radioisotope Products and Radiation Technology Section (RIRT), Vienna, Austria,
[email protected]
1
Abstract:
The International Atomic Energy Agency under Nuclear Applications program actively supports radionuclide
production, radiopharmaceutical production programs, and associated human resource development for safe
and efficacious use in clinical and research applications. The lecture will also highlight the training and
education initiatives currently under progress under IAEA.
34
4th-INCC 2014 I 4th International Nuclear Chemistry Congress
RADIOPHARMACEUTICALS PRODUCTION AT IPEN/CNEN-SP
Regina Célia Gorni Carneiro1
Radiopharmacy Center – Institute of Energetic and Nuclear Research – IPEN-CNEN/SP, São Paulo, Brazil, regina.carneiro@
ipen.br
1
The use of radioisotopes in medicine is certainly one of the most important social applications of Nuclear
Energy. IPEN, and particular the Radiopharmacy Center, has a special place in the history of Nuclear
Medicine in Brazil.
The production of radioisotopes and radiopharmaceuticals for use in Nuclear Medicine started with 131I
in the late 50s at IPEN. Since then there has been a significant and constant increase in the demand for
diagnostic and therapeutic radiopharmaceuticals over the years and nowadays 38 products are in routine.
Due to this production Brazil reached over 2 million nuclear medical procedures in 380 Diagnostic Clinics,
Hospitals and Center of nuclear medicine.
The Radiopharmacy Center is organized in six activities areas: Production; Quality Assurance; Quality
Control; Research, Development and Innovation; Infrastructure and Maintenance Support; and Cyclotron
Accelerator.
The Production area carries out the everyday production of 10 primary radioisotopes, 12 labeled molecules
and 16 lyophilized kits for labeling with 99mTc. The Cyclotron Accelerator Division is responsible for the
operation of two Cyclotrons (18 and 30 MeV) and carries out the irradiation for obtaining the cyclotronproduced radioisotopes such as 18F and 123I. Year by year the demand for 99Mo/99mTc Generator production has
been increased, nowadays the Radiopharmacy Center produces 400 generators per week. Besides, the 131I
solution and 131I capsule production was increased, however the production of 18F-FDG was decreased due
to the assembling of new PET production centers.
New radiopharmaceuticals are in developing such as Bombesin derivatives labeled with 90Y and 177Lu, 177LuAnti-CD-20; 64Cu-ATSM, HYNIC-TATE, MAG3 for labeling with 99mTc. These radiopharmaceuticals are in
stages of pre clinical and clinical trials and soon they will be offered for the nuclear medicine community.
Through a program of continuous progress the Radiopharmacy Center improves its facilities, equipment,
human resources and upgrades the technologies involved to meet the growth of the Brazilian market
radiopharmaceuticals applied in diagnostics and therapy. Relying on employees with specialized and skilled
training in Radiopharmacy and related areas, seeks to maintain the state of art in the development of new
radiopharmaceuticals.
35
4th International Nuclear Chemistry Congress I 4th-INCC 2014
IMPORTANCE OF NEUTRON ACTIVATION IN SPECIATION ANALYSIS
Amares CHATT1
1
Trace Analysis Research Centre, Department of Chemistry, Dalhousie University, Halifax, Canada, [email protected]
Speciation analysis is defined by IUPAC as the “analytical activities of identifying and/or measuring the
quantities of one or more individual chemical species in a sample” [1]. It covers many areas including
oxidation states of an element and distribution of an element among different inorganic, organometallic as
well as macromolecular compounds. Neutron activation analysis (NAA) is a well-established analytical
technique for the simultaneous determination of many elements. We have significantly extended the scope
of NAA over the last two decades or so by incorporating chemical methods to determine several species
at the same time and called it simultaneous speciation NAA (SSNAA). In SSNAA we have exploited a
number of advantageous features of NAA such as simultaneous multielement specificity, determination of
elements which are chemically dissimilar, measurement of elements which are rather difficult to determine
by most other analytical techniques, and unique and enhanced quality assurance features which many other
techniques lack.
In this lecture we will describe some of the methods developed in our laboratory using the Dalhousie
University SLOWPOKE-2 reactor facility to separate, detect, identify and measure various chemical
species of elements, to investigate the possibility of interconversion of elements, and to study simultaneous
multielement speciation. We will discuss relative expanded uncertainties of measurements for some species
by SSNAA.
We will demonstrate the effectiveness of NAA for speciation analysis using three projects. We will cover
SSNAA methods to assay low levels of various arsenic species, namely As(III), As(V), monomethylarsonic
acid (MMA), dimethylarsinic acid (DMA), and arsenobetaine (AsB), as well as organically bound arsenic
(OBAs), lipid-soluble arsenic (LSAs) and total arsenic in water and marine samples. We recently extended
these methods to include simultaneous determination of various species of As, Sb and Se in water samples
and studied interconversion of species. We have also developed NAA methods in conjunction with MS,
GC-MS, LC-MS, MS-MS, NMR for the simultaneous separation and characterization of extractable
organochlorine, organobromine and organoiodine proteic and lipidic species in fisheries samples. These
halogen compounds are not conveniently quantified by other analytical techniques such as AAS and ICP-MS.
We have used analytical and bioanalytical techniques such as dialysis, pH variation, ammonium sulphate
precipitation, ion-exchange, hydroxyl apatite and size-exclusion chromatography, HPLC, chromatofocusing,
isoelectrofocusing and isotachophoresis, complemented by NAA to study macromolecular species of As,
Br, Ca, Cl, Cu, Fe, I, K, Mg, Mn, Mo, Na, Rb, S, Se, V, and Zn in bovine kidneys. The details of the methods
together with the results will be presented.
REFERENCES
1) D.M. Templeton, F. Ariese, R. Cornelis, L-G. Danielsson, H. Muntau, H.P. Van Leeuwen, R. Tobiński, Pure Appl Chem,
72(2002)1453
36
4th-INCC 2014 I 4th International Nuclear Chemistry Congress
MANAGEMENT OF BY-PRODUCTS GENERATED BY NORM INDUSTRIES:
TOWARDS THEIR VALORIZATION AND MINIMIZATION OF THEIR
ENVIRONMENTAL IMPACT
Rafael García-Tenorio1
1
Centro Nacional de Aceleradores (Universidad Sevilla, J. Andalucía, CSIC), Sevilla, Spain, [email protected]
The processing in some paradigmatic industries of raw materials enriched in natural radionuclides, called
NORM (Naturally Occurring Radionuclide Materials) industries, generates in addition to main commercial
products, huge amounts of by-products which historically have not deserve commercial attention. On the
contrary, generally these by-products have either been released to the environment or disposed under control
in big areas, producing in both cases a clear environmental and even in some cases public radiological
impact.
The tendency to the disposal of the commented by-products have been influenced by the presence in them
of moderate amounts of natural radionuclides that have induced historically to erroneous conclusions in
relation to its potential radiological impact in the public. At the same time the risks associated to the disposal
have been minimized and/or neglected.
In this talk, and following the actual recommendations given by the IAEA in the new Basic Safety Standards,
the policy of finding valorization to these by-products will be highlighted. As it will be demonstrated, this
policy produces in most cases economical benefits to the involved company and to the society and at the
same time minimizes the environmental and radiological public impact of these by-products.
Two examples will support the recommended policy of NORM by-product valorization. a) The use of
phosphogypsum (the main by-product generated in the production of phosphoric acid by the wet-acid
method) in agriculture for the reclamation of saline soils, b) The transformation (avoiding its release to
the deep sea), in two products with commercial value and well defined market of the huge amounts of
strong acids generated in the production of titanium dioxide pigments by the so-called sulphate method. The
benefits obtained for the valorization of these by-products from an environmental and radiological point of
view will be supported by the detailed radiometric and radiological studies that we have performed in both
cases.
37
4th International Nuclear Chemistry Congress I 4th-INCC 2014
Metrology in chemistry at the IJS/O-2: advantages and
disadvantages
Radojko JAĆIMOVIĆ1, Milena Horvat1, Polona VREČA1, Vekoslava Stibilj1, Tea Zuliani1
1
Department of Environmental Sciences, Jožef Stefan Institute, Ljubljana, Eslovenia, [email protected]
The metrology system of the Republic of Slovenia is based on distributed system with nine designated
institutes (DIs) to perform defined activities in the field of scientific and legal metrology. Activities are
coordinated by Metrology Institute of the Republic of Slovenia (MIRS). In Slovenia, all DIs must be
accredited according to the standard ISO/IEC 17025. The Department of Environmental Sciences of the
Jožef Stefan Institute (IJS/O-2) currently has four methods accredited under accreditation certificate LP-090
given by Slovenian Accreditation (SA) agency. One of the accredited methods is k0-instrumental neutron
activation analysis (k0-INAA) for the determination of 31 elements in samples from environment, foodstuffs,
agricultural products and biological samples.
In 2010 the IJS/O-2 has been designated as a holder of national measurement standard in the field of
Metrology in Chemistry for the amount of substance in soils, sediments, ores, sewage sludge, based on
the BIPM “List of amount of substance categories” (http://kcdb.bipm.org/AppendixC/QM/QM_categories.
pdf). This status of IJS/O-2 as DI is evidenced at the BIPM database (http://www.bipm.org/en/cipm-mra/
participation/signatories.html), as well as at the MIRS web page (http://www.mirs.gov.si/en/). This allowed
us to participate in key and supplementary comparisons of the CCQM (Consultative Committee for Amount
of Substance – Metrology in Chemistry), APMP (Asia-Pacific Metrology Programme), etc. and in their
pilot studies. Participation in CCQM key comparisons may open the door to publishing the calibration and
measurement capabilities (CMCs) of the lab in Appendix C of the BIPM key comparison database (KCDB)
under the Mutual Recognition Arrangement of the International Committee for Weights and Measures
(CIPM MRA), maintained by the BIPM and available on the Internet. To have our own CMCs is important
not only at national level, but also to justify the status of DI in the KCDB. Unfortunately, until 2005 no
CCQM study in the BIPM category for which IJS/O-2 is designated has been organized. Although we
have participated with great success in numerous KC for other matrices, we cannot officially demonstrate
calibration and measurement capability. In the real terms of metrology principles in chemistry the usefulness
of the BIPM list for the amount of substance categories is questionable, especially in case the analytical
method is not matrix dependant, such as INAA.
The k0-INAA method used at our Institute is multielement technique and in principle independent from
sample matrix. For more than 20 years the k0-INAA is in use at our Institute and we participated in
characterization studies for new certified/reference materials from different producers and in seven CCQM
interlaboratory studies. The results obtained were in very good agreement with assigned values, regardless
of the matrix, which confirms the above statements and argues for re-consideration of the BIPM list of
amount of substance categories.
38
4th-INCC 2014 I 4th International Nuclear Chemistry Congress
Brazilian Multipurpose Reactor, a structuring enterprise for the
nuclear area
José Augusto Perrotta1
Comissão Nacional de Energia Nuclear, São Paulo, Brazil, [email protected]
1
Brazil has four research reactors (RR) in operation: IEA-R1, a 5 MW pool type RR; IPR-R1, a 100 kW
TRIGA type RR; ARGONAUTA, a 500 W Argonaut type RR, and IPEN/MB-01, a 100 W critical facility.
The first three were constructed in the 50’s and 60’s, for teaching, training, and nuclear research, and for
many years they were the basic infrastructure for the Brazilian nuclear developing program. The last,
IPEN/MB-01, is the result of a national project developed specifically for qualification of reactor physics.
Considering the relative low power of Brazilian research reactors, with exception of IEAR1, are not feasible
for regular radioisotope production, and even IEA-R1 has a limited capacity. As a consequence, the Mo-99
needed to attend Brazilian nuclear medicine services has been imported. Because of the high dependence
on external supply, the international Mo-99 supply crisis that occurred in 2008/2009 affected significantly
Brazilian nuclear medicine services, and in 2010 the Brazilian Nuclear Commission decided to build a new
research reactor. The new reactor named RMB (Brazilian Multipurpose Reactor) will be a 30 MW open
pool type reactor, using low enriched uranium fuel. The facility will be the centre of a new nuclear research
institute, to be built about 120 kilometres from São Paulo city, in the southeast part of Brazil. Besides of
producing radioisotope for medical application, the complex will have several facilities: to use thermal
and cold neutron beams; to produce radioisotopes for several applications; to perform neutron activation
analysis; and to perform irradiation tests of materials and fuels. Regarding to neutron beam application, the
complex is viewed as a national laboratory in complement to the Synchrotron Light National Laboratory.
The presentation will focus on the main characteristics of the new complex, with emphasis on the laboratory
for neutron activation analysis, and the current status of the project.
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
High-flux Prompt-Gamma Activation Analysis at FRM II, Garching
Zsolt Révay1
Technische Universität München, Forschungsneutronenquelle Heinz Maier-Leibnitz (FRM II), [email protected]
1
At the Research Neutron Source Heinz Maier-Leibnitz (FRM II) in Garching, the PGAA facility operates
the strongest reported neutron beam, with a flux of 6x1010 cm-2 s-1, which almost reaches the flux of smaller
reactors. The focused cold neutron beam makes possible plenty of new applications, which were impossible
earlier when using this technique. The sample masses can now be below 1mg, or materials with extremely
low cross section (such as deuterium [0.5 mb], oxygen [0.2mb], or even gasous neon [39mb]) can be
measured with good statistics. In this beam, even radioactive samples can be irradiated whose induced
activity was found to be too low to compete with the natural activity. Moreover, in-beam neutron activation
analysis (NAA) can also be performed. This method can be combined with PGAA, significantly increasing
the number of detectable elements. In the talk, the methodological developments and the most important
applications will be summarized.
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4th-INCC 2014 I 4th International Nuclear Chemistry Congress
RADIOCHEMISTRY TECHNIQUES USED IN CHARACTERIZATION OF
RADIOACTIVE WASTES
Maria Helena Tirollo Taddei1
1
Comissão Nacional de Energia Nuclear – Laboratório de Poços de Caldas, Poços de Caldas, Brazil, [email protected]
Regulations regarding transfer and final disposal of radioactive waste require that the inventory of
radionuclides for each container enclosing such waste must be estimated and declared. The regulatory limits
are established as a function of the annual radiation doses that members of the public could be exposed to
from the radioactive waste repository, which mainly depend on the activity concentration of radionuclides,
given in Bq/g, found in each waste container. Most of the radionuclides that emit gamma-rays can have
their activity concentrations determined straightforwardly by measurements carried out externally to the
containers. However, radionuclides that emit exclusively alpha or beta particles, as well as gamma-rays
or X-rays with low energy and low absolute emission intensity, or whose activity is very low among
the radioactive waste, are generically designated as Difficult to Measure Nuclides (DTMs). The activity
concentrations of these DTMs are determined by means of complex radiochemical procedures that involve
isolating the chemical species being studied from the interference in the waste matrix.
The presente work describes the determination of some DTM radionuclides of the elements strontium,
uranium, neptunium, plutonium, americium, curium, iron, nickel, carbon, trtium and silver from ionexchange resins and activated charcoal beds that were withdrawn from the water cleanup system of the
IEA-R1 nuclear research reactor.
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
THE PRESENT STATUS OF NUCLEAR CHEMISTRY EDUCATION IN DIFFERENT
UNIVERSITIES AND COUNTRIES
Turan ÜNAK1
1
International Nuclear Cheistry Society (INCS), Izmir, Turkey, [email protected]
In last two decades, the educational problems envisaged in nuclear chemistry and the challenges faced by
professionals in this field have been voiced at different meetings and scientific platforms and a number of
reports have been published [1-2]. Unfortunately, it is difficult to say how these efforts have practically
affected and changed the situation in a positive manner. Here, it is hoped to summarize the present status of
nuclear chemistry education across the world and to examine how some concrete efforts can be made by the
professionals in this field to encourage a better understanding this undesirable situation and to improve it.
As it is well known, several worldwide ranking systems for universities operate and top world universities
are scored. According to the 2013 - 2014 World University Rankings, the top 5 universities are as follows:
1st California Institute of Technology (USA),
2nd University of Oxford (UK),
3rd Stanford University (USA),
4th Harvard University (USA),
5th Massachusetts Institute of Technology, MIT (USA).
In 2012 – 2013 these results were the same, but were slightly different in earlier years. These top universities
have undergraduate and graduate chemistry programs in their various departments. Unfortunately, these
programs do not include nuclear chemistry courses or other courses with titles based on nuclear phenomena
or which study nuclear radiation or its applications. This is a very problematical situation and the reasons
for this very important omission need to be very carefully evaluated.
The chemistry programs of top 50 universities were carefully browsed and it was observed that while
some universities have some courses in their undergraduate and / or graduate programs with different titles,
such as Radioisotope techniques (in Analytical chemistry), Nuclear chemistry (in Inorganic chemistry),
Radiochemistry, Radiopharmacy, Radiation chemistry of polymers, Chemistry of nuclear fuel cycling,
Radiation chemistry, Nuclear and medicinal inorganic chemistry, etc., the majority of universities do not
run any courses related to nuclear chemistry and / or its applications.
In spite of this, some universities which are far from the top of the ranking do run very intensive courses
related to nuclear chemistry and / or its applications. It seems clear that the activities of these universities are
closely connected with the personal activities of some of the well known names in nuclear chemistry who
are employed as faculty staff in these universities.
This short overview of nuclear chemistry education programs has reached some important conclusions:
1)
Nuclear chemistry education has not yet achieved classical status in chemistry curriculums
worldwide like organic chemistry, analytical chemistry, inorganic chemistry, physical chemistry or
biochemistry;
2)
The majority of active chemistry staff do not have not enough knowledge of nuclear chemistry,
which results in the formulation of chemistry curriculums which do not include nuclear chemistry courses,
3)
This status prevents the education of new staff in nuclear chemistry and so creates a vicious
circle for the subject,
4)
The good examples which are encountered can be attributed to the personal efforts of some
well educated staffs in nuclear chemistry and this does not guarantee that the same status will continue in
the future.
Some practical remedies for this situation:
1)
Today’s active nuclear chemistry staffs should understand that they have been charged with a
very important mission for the future status of nuclear chemistry and that they need to be much more active
42
4th-INCC 2014 I 4th International Nuclear Chemistry Congress
and try to help other chemistry staffs in their universities to understand that nuclear chemistry education
should have a permanent place in chemistry curriculums without depending on temporary personnel efforts
and activities;
2)
Nuclear chemistry staffs should communicate with all national or international scientific
organizations to spread more understanding of the important role of nuclear chemistry in the scientific and
technological applications required for future human life;
3)
The number of civil national and international organizations such as INCS and the
Radiochemistry Society in the USA should be increased;
4)
A master program for nuclear chemistry needs to be formulated and recommended for
introduction into all chemistry curriculums in various universities across the world. This would help to
create more interest in the field of nuclear chemistry among the younger generation.
REFERENCES
1)Assessment of the teaching and applications in radiochemistry, Reporter: M. Rössbach, IAEA Report of a technical meeting,
10 - 14 June 2002, Antalya, Turkey.
2)Round table discussion panel report, Reporter: T. Ünak, 1st-INCC, 22 - 29 May 2005. Kusadasi, Turkey.
43
4th International Nuclear Chemistry Congress I 4th-INCC 2014
THE USE OF INAA IN THE DEVELOPMENT AND CERTIFICATION OF NIST
BIOLOGICAL STANDARD REFERENCE MATERIALS
Rolf Zeisler1
1
National Institute of Standards and Technology, Gaithersburg, USA, [email protected]
Substantial development of biological and environmental Standard Reference Materials (SRMs) by the
National Institute of Standards and Technology (NIST) (then the National Bureau of Standards) began in
the early 1970s. Starting with the production and certification of the firstever, natural matrix, multi-element
botanical Standard Reference Material (SRM) 1571 Orchard Leaves, issued in 1971, and followed by SRM
1577 Bovine Liver in 1972, the determination of key biological and contaminant elements, including Ca,
Mg, Fe, Cu, Zn, Se, Cr, Cd, As, Pb, and Hg could be validated using quality assurance materials. The
certification was accomplished using a broad array of analytical methods, with neutron activation analysis
(NAA) having contributed to the majority of certified values. The needs for more diverse and extensively
characterized SRMs to fulfill the ever-growing demands in analytical chemistry for life science research
and applications have been the driving force for refinement and expansion of the program. Concurrent with
this development, NAA transitioned rapidly to instrumental multi-element procedures (INAA) based on
high-resolution gamma-ray spectrometry. Today, while radiochemical (RNAA) procedures are still utilized
in determinations requiring highest sensitivity, INAA procedures have been developed to highest versatility
and performance and are accepted as primary method of measurement1.
An illustration of the continued importance of particular SRMs is given by the series of issues of SRM
1577 with SRM 1577c, which maintain a benchmark position in the NIST SRM program. Other recent key
developments discussed in this context include SRM 3280 Multivitamin/Multielement Tablets and candidate
SRM 2791 Inorganic Constituents in Soft Wood Biomass Material. A relatively new area is the development
of methods for the separation and quantification of arsenic species in SRM 2669 Arsenic Species in Frozen
Human Urine as well as in candidate SRM 3232 Kelp. By combining INAA with liquid chromatography
and inductively coupled plasma mass spectrometry (LC-ICP-MS) a roadmap leading to the certification of
the latter material is being developed.
REFERENCES
1) R. R. Greenberg, P. Bode, E. A. Fernandes, Spectrochim Acta B 66 (1970) 193.
44
Oral Session
Session 1 - Radiopharmaceutical Chemistry
4th-INCC 2014 I 4th International Nuclear Chemistry Congress
FULVI-H AS HUMAN DIETARY SUPPLEMENT
Juan Manuel Navarrete Tejero1, Omar Yahir Morales1, Maria Isabel Gracia Mora1, Miguel
Angel Zúñiga Pérez1
Universidad Nacional Autónoma de México - UNAM, México, D. F., Mexico, [email protected]
1
Fulvi-H is Fulvic acid produced and sold in Mexico, firstly as soil fertilizer and secondly as animal dietary
supplement1. Now, after high purification from heavy metals and bacterial organisms, it has been authorized
as human dietary supplement, in view of empirical excellent results in all fields, as well as experimental
results obtained with mice and rats, which showed much better filtration of electrolytes through liver from
digestive pipe to blood serum (32PO43-, 45Ca2+, 59Fe3+, 131I1-) followed by promotion of antibodies in their
immune system (IgG, IgT)2,3. This paper summarizes all these results and proposes Fulvi-H at higher doses
as a valuable complement in addition to treatment of human viral diseases, such as Herpes Zoster, Hepatitis
C and AIDS. Therefore, next step should be a medical protocol, to test the facts proved in laboratory animals.
REFERENCES
1) O. Y. Morales, J. M. Navarrete, I Gracia, L. Macías, M. Rivera, F. Sánchez, Nuclear Instruments and Methods in Physics
Research A 652-1 (2011) 838.
2) O. Y. Morales, J. M. Navarrete, I. Gracia, L. Macías, M. Rivera, F. Sánchez, The Open Conference Proceedings Journal, 3
(2012) 24.
3) O. Y. Morales, J. M. Navarrete, I. Gracia, L. Macías, M. Rivera, F. Sánchez, J. Radioanal. Chem. 299 (2014) 839.
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
COMPARISON OF 99mTc ACTIVITY MEASUREMENTS AT LNMRI USING
SIRTI OF THE BIPM, A NEW INSTRUMENT FOR COMPARING SHORT-LIVED
RADIONUCLIDES
Paulo Alberto Lima da CRUZ1, Carlos José da Silva1, Denise Simões Moreira1, Adilson da Silva
Laranjeira1, Akira Iwahara1, Luiz tauhata1, Ricardo Tadeu Lopes2
Instituto de radioproteção e Dosimetria, 2COPPE/UFRJ , Rio de Janeiro, Brazil, [email protected]
1
Technetium-99m is the most widely used radionuclide for obtaining diagnostic imaging in Brazilian nuclear
medicine centers and its demand is growing every year. In order to provide metrological traceability to
producer and end users of 99mTc in Brazil to fulfil nuclear regulatory requirements for radiopharmaceuticals,
the National Metrology Laboratory for Ionizing Radiation (LNMRI) attended, in 2013, a comparison of
activity measurement of 99mTc through the Bureau International des Poids et Mesures (BIPM) program called
Transfer Instrument of the International Reference System (SIRTI). This program allows National Metrology
Institute (NMI) can compare your results with other NMIs and thus establishing traceability internationally
through the BIPM key comparison. The 4pβ(LS)-g (NaI) anticoincidence primary measurement method
was used and the result was validated by CIEMAT/NIST and TDCR liquid scintillation methods. The
measurement methods and the SIRTI are briefly described. The measurement results and the degree of
equivalence between the key comparison reference value (KCRV) and the LNMRI value are presented. The
LNMRI result reported agreed with the SIRTI equivalent activity within one standard uncertainty1.
REFERENCE
1) C. Michotte, M. Nonis, P. Arenillas, G. Cerutti, C. J. da Silva, P. A. L. da Cruz, D. S. Moreira, A. Iwahara, J. U. Delgado, R.
Poledna, R. L. da Silva, A. E. de Oliveira, R. dos S. Gomes, Metrologia 50 (2013) 1.
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4th-INCC 2014 I 4th International Nuclear Chemistry Congress
New potential for treatment of Wilson`s disease
Miroslav Vetrík1, Jan Kučka1, Michaela SKODOVA1, Jana Matova2, Pavla Poučková2,
Petr Stepánek1, Petr Urbánek2, Milos Petrík3, Zbynek Nový3, Martin Hrubý 1
Institute of Macromolecular Chemistry AS CR v.v.i., 2Institute of Biophysics and Informatics, First Faculty of Medicine, Charles
University in Prague, 3Institute of Molecular and Translational Medicine, Faculty of Medicine and Dentistry, Prague, Czech
Republic, [email protected]
1
Wilson`s disease is a genetic disorder leading to high accumulation of copper in organism. The accumulated
copper causes toxic effects that manifestate as neurological and psychiatric symptoms and/or liver
disease. Prevalence of Wilson`s disease in population is 1 to 4 per 100,000.1 Current therapy based on
penicillamine, trientine hydrochloride and in special cases dimercaprol suffers from severe side effects.
We propose a new treatment to eliminate the excessive copper content in human body.2 The treatment
is based on oral administration of insoluble and non-resorbable polymer sorbents synthesized from
poly(glycidyl methacrylate-co-ethylene dimethacrylate) containing selective chelating groups for copper
(II). Polymeric macroporous beads with the chelating agents triethylenetetramine, N,N-di(2-pyridylmethyl)
amine, 8-hydroxyquinoline-5-sulfonic acid or 8-hydroxyquinoline (8HQs), respectively, were investigated.
We found that 8HQs efficiently reduced copper uptake (64Cu as radiotracer) after oral administration in
Wistar rats as confirmed by both PET/CT imaging and organ radioactivity measurement after sacrifice of
the animals. The beads with bound copper are stable within wide range of pH. Gastrointestinal absorption
of the polymer was determined by radioactivity measurement of mice`s organs after oral administration of
radiolabeled 125I-8HQs, no significant uptake from gastrointestinal tract was found. We are now studying
polymer-supported new cyclam-based chelators and their kinetic of chelatation of 64Cu as potential chelatin
moieties for our new Wilson`s disease treatment.
This work was supported by the Grant Agency of the Czech Republic (grants # 13-08336S and P304/12/0950)
and by Academy of Sciences of the Czech Republic (grant # M200501201).
REFERENCES
(1) A. Aftab, A.P. Walker, K. Ashkan, J.S. Dooley, M. L. Schilsky, Lancet 369 (2007) 9559
(2) M. Škodová, J. Kučka, M. Vetrík, J. Skopal, Z. Walterová, O. Sedláček, P. Štěpánek, J. Mattová, P. Poučková, P. Urbánek,
M. Hrubý, React. Funct. Polym. 73 (2013) 1426.
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
RADIONUCLIDE LABELLED NANOPARTICLES
Perihan Unak1
Department of Nuclear Applications, Institute of Nuclear Sciences, Ege University , Izmir, Turkey, [email protected]
1
Innovation in the last decade has accomplished nanotechnology with an variety of tools for delivery,
imaging, and sensing in cancer research—crafty nanoparticle vectors circulating in vivo, assembled with
delicate molecular control, capable of selective tumor targeting and potent delivery of therapeutics; intense
and photostable quantum dot-based tumor imaging, enabling multicolor detection of cell receptors with a
single optical excitation source; arrays of semiconducting nanowire and carbon and boron nitride nanotube
sensor elements for selective multiplexed sensing of cancer markers without the need for probe labeling.
These rapidly emerging tools are indicative of a promising field ready to expand into medical applications.
Primary healthcare fields currently leveraging the technologies are;
1. Bio-medical, particularly in the areas of tumor detection and treatment
2. Pharmaceutical, for delivery of treatment at a cellular level
3. Research, primarily in determining causes and detection of diseases affecting the central nervous
system (e.g. Alzheimer’s and Parkinson’s)
Radionuclide labeling supplies nanoparticles additional property to trace in molecular imaging. The update
review of radionuclide labeled nanoparticles in Ege University will be outlined in this presentation. The
selected radionuclides are radioiodine (125/131I), 18F and 99mTc. Magnetic, gold nanoparticles, quantum dots
have been synthesized and used to conjugate several ligands such as antibodies, lectins, estrogen ligands etc.
52
Session 2 - Radioanalytical Chemistry
4th-INCC 2014 I 4th International Nuclear Chemistry Congress
COMPARATIVE STUDY OF INORGANIC ELEMENTS DETERMINATION IN
WHOLE BLOOD FROM Dmdmdx/J MICE STRAIN BY EDXRF AND NAA ANALYTICAL
TECHNIQUES
Marcelo Miyada Redígolo1, Ivone Mulako Sato1, Sabrina Metairon2, Cibele Bugno
Zamboni2
Instituto de Pesquisas Energéticas e Nucleares - Centro de Química e Meio Ambiente, 2Instituto de Pesquisas Energéticas e
Nucleares – Centro de Reatores de Pesquisa, São Paulo, Brazil, [email protected]
1
Several diseases can be diagnosed observing the variation of specific electrolytes concentration in blood.
Then, the determination of metals and ions in body fluids, such as Ca, Cl, K and Na, are relevant for clinical
chemistry. Those elements are also important in veterinary medicine, specifically, in public health studies,
which utilize animal models for medical diagnostic studies before testing human beings. Based on this, this
study focuses on the anomalies caused by Duchenne Muscular Dystrophy (DMD), which is an illness of
hereditary character. Its main characteristic is the degeneration of the membrane that involves the muscular
cell, causing its death. All forms of muscular dystrophy are genetic; cannot be prevented or reverted. The
DMD is the most common of them. In this work, whole blood samples of Dmdmdx/J (9 males and 10 females)
dystrophic mice and C57BL/6J (10 males) control group mice’s model (genetically modified) used for
muscular dystrophy investigations were analyzed by the EDXRF technique. The reference interval values
were determined for Ca, Cl, K, Mg, Na and S elements and a comparative study with NAA results was
outlined. The samples were obtained from Instituto de Pesquisas Energéticas e Nucleares, Instituto Butantan
and Centro de Estudos do Genoma Humano do Instituto de Biociências (Research Centers, Brazil). The
EDXRF and NAA analytical techniques, showed to be appropriate for whole blood sample analyses and
offer a new contribution for studies in Veterinary Medicine related to biochemical analyses of blood.
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
Sodium determination in NIST SRMs 1515 Apple Leaves and 1547 Peach
Leaves by INAA: What has happened with the sodium certified
values?
Jan Kucera1, Jan Kamenik1
Nuclear Physics Institute ASCR, Husinec-Rez, Czech Republic, [email protected]
1
When using NIST SRMs 1515 and 1547 as quality control samples in various studies using INAA in last
couple of years, we were finding significantly higher sodium contents compared with the NIST certified values
of 24.4 ± 1.2 μg g-1 and 24 ± 2 μg g-1. Our values have been higher by 30--40 %. Similarly high values were
reported from other laboratories using various analytical techniques, although some laboratories reported
results in agreement with the NIST certified values. Therefore we have conducted an INAA study aiming
at elucidation of the above differences. In this study we analyzed four 200 mg aliquots of NIST SRM 1515
taken from one original glass NIST bottle after sampling the top layer and after rolling the bottle to evaluate
the possible contamination of the surface layer, and one aliquot from a polyethylene (PE) vial, which was
delivered to our laboratory for an interlaboratory comparison organized by NIST prior to certification of
this material in 1993. Concerning NIST SRM 1547, four 200 mg aliquots were taken from the original glass
NIST bottle purchased about 10 years ago and from another original NIST bottle purchased in 2010 using
the same sampling techniques as above. However, insufficient amount of material sent to our laboratory for
the above intercomparison was available. For quantification, NIST SRM 3152a Sodium Standard Solution
was employed as calibrant. All possible source of bias, such as apparent Na content from the 24Mg(n,p)24Na
and 27Al(n,α)24Na nuclear reactions with fast neutrons, blank originating from PE irradiation vials, and
neutron flux gradient within the irradiation vial were corrected for. The results for NIST SRM 1515 and
NIST SRM 1547 for aliquots taken from the NIST original bottles yielded the overall mean ± s.d. of 33.4 ±
2.5 μg g-1 and 33.5 ± 1.5 μg g-1, respectively, while the Na content determined in the “old” NIST SRM 1515
aliquot was 21.6 ± 0.3 μg g-1, which is rather close to the original NIST certified value. These results prove
that Na contents in the NIST SRMs studied changed with time for yet unknown reason.
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4th-INCC 2014 I 4th International Nuclear Chemistry Congress
Model-Age Determination of Nuclear Forensic Materials by Mass
Spectrometry
Gary Richard Eppich1, Ross W. Williams1, Ian D. Hutcheon1
Chemical Sciences Division, Lawrence Livermore National Laboratory, Livermore, USA, [email protected]
1
The illicit trafficking of uranium and plutonium presents a significant threat to global security. Nuclear
forensic analysis, alongside conventional forensics, can be used to determine the source, fate, and intended
use of interdicted nuclear materials, greatly aiding the effort of law enforcement and international regulatory
agencies in preventing nuclear trafficking. The production age of an interdicted sample is an intrinsically
useful datum in a nuclear forensic investigation, as it does not require comparison against a database. Recent
advances in nuclear material age determination using mass spectrometry1-4 have increased the precision of
ages to hundreds of days or less, in ideal cases. The age of the sample is, in nuclear materials, interpreted
as the time of most recent uranium and/or plutonium purification, and is referred to as a “model-age”
because it is dependent on assumptions of: 1) closed-system behavior, where no loss or gain of parent and/
or daughter nuclides has occurred other than through the decay of parent and ingrowth of daughter; and
2) the initial concentration of daughter nuclides at the time of most recent purification was zero. Here we
present the current state of the art in model-age determination methods for nuclear forensic investigations.
Nuclear forensic samples are dissolved, and aliquots of the dissolved samples are spiked with calibrated
233
U, 244Pu, 229Th, 233Pa, and 243Am spikes. Uranium, Pu, Th, Pa, and Am are purified using a sequence
of ion exchange chromatography procedures, allowing for high-precision analysis using a Nu Plasma
multicollector inductively-coupled plasma mass spectrometer. Model-ages are calculated on the basis of
parent and daughter concentration at the time of analysis, and age uncertainty is calculated rigorously and
conservatively. As an example, we present 234U-230Th, 235U-231Pa, and 241Pu-241Am model age results from
a case study, and discuss implications of concordant and discordant ages in reaching nuclear forensics
conclusions.
REFERENCES
1)S. P. Lamont, G. Hall, J. Radioanal. Nucl. Ch. 264 (2005) 423.
2)Z. Varga, G. Surányi, Anal. Chim. Acta 599 (2007) 16.
3)R. W. Williams, A. M. Gaffney, Proc. Radiochim. Acta 1 (2011) 31.
4)G. R. Eppich, R. W. Williams, A. M. Gaffney, K. C. Schorzman, J. Anal. Atom. Spectrom. 28 (2013) 666. This work
performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Laboratory under Contract
DE-AC52-07NA27344. LLNL-ABS-654656.
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
LOW BACKGROUND NEUTRON ACTIVATION ANALYSIS: A POWERFUL TOOL FOR
ENVIRONMENTAL SCIENCES AND PHYSICS OF RARE EVENTS
Massimiliano Clemenza1,2, Giovanni Baccolo2,3,4, Barbara
Maffezzoli1,2, Valter Maggi2,3, Ezio Previtali1,2, Elena Sala1,2
Delmonte3,
Niccolò
Physics Department, University of Milano-Bicocca, 2INFN sezione di Milano Bicocca, 3Environmental Sciences Department,
University of Milano-Bicocca, 4University of Siena, Milan, Italy, [email protected]
1
Instrumental Neutron Activation Analysis (INAA) is a common method of trace element analysis [1] whose
sensitivity depends, as with almost all the analytical techniques used in the various fields of research, from
the signal to noise ratio. In the case of INAA the sensitivity is limited by interference from other trace
elements (and in some case from major elements) in the sample, or by interference from ambient background
radiation in the detection system. Usually the first choice is to maximize the signal by increasing all those
parameters, which in principle can be improved as much as possible in sample irradiation process and in
gamma spectroscopy measurements such as neutron flux intensity, irradiation-waiting-measuring times,
detector efficiency, sample mass. The Low Background Neutron Activation Analysis (LBNAA) foresee to
minimize all sources of noise that limit the sensitivity of the technique, as the contamination in materials
containers used during sample irradiation, the radioactive background due to the major and minor elements
of the sample matrix, through radiochemical techniques, radioactive background suppression methods
(gamma-gamma coincidences) as well as the use of detector with very low intrinsic radioactive background
and the selection of containers made with high purity materials. In particular are showed two cases of
application of LBNAA in two different areas of research such as the materials selection for physics of
rare events experiments (Double Beta Decay and Dark Matter search [2,3] ) and the ultra-trace elements
analysis in Antarctic and Alpine ice cores samples (see also G. Baccolo abstract).
REFERENCES
[1] G. Baccolo, C. Baroni, M. Clemenza, et al J. Radioanal. Chem. Vol. 299 (2014) p. 1615-1623
[2] F. Alessandria et al. The low energy spectrum of TeO2 bolometers: results and dark matter perspectives for the CUORE-0
and CUORE experiments. Journ. of Cosm. and Astropart. Phys., (2013) vol. 2013; p. 038-038, ISSN:
[3] F. Alessandria et al. CUORE crystal validation runs: Results on radioactive contamination and extrapolation to CUORE
background. ASTROPARTICLE PHYSICS. (2012) vol. 35; p. 839-849,
58
Session 3 - Education in Nuclear Chemistry/
Radiopharmaceutical Chemistry
4th-INCC 2014 I 4th International Nuclear Chemistry Congress
RADON INDOOR MEASUREMENTS A WAY TO EDUCATE TO NUCLEAR ISSUE:
ITALIAN RADIOLAB PROJECT
Flavia Groppi1, Mauro L. Bonardi1, Simone Manenti1, Luigi Gini1, Anna Bazzocchi1,2
Università degli Studi di Milano & INFN, Physics Department – LASA Laboratory, 2Itis Mattei, San Donato Milanese (MI), ,
Milan, Italy, [email protected]
1
Since 2005 in Italy two programs were promoted from Ministry of Education and University and National
Institute of Nuclear Physics (INFN) for scientific dissemination in the field of environmental radioactivity,
devoted to High School students in many Italian regions that were involved in particular in indoor radon
measurements. The idea of this project started from the consideration that the subjective perception (sensation)
of the risk doesn’t correspond very often to the objective and real risk of human activity. In particular,
our perception of radioactivity is often misleading because of the lack of accurate information. A way to
approach this theme, to make the public more trusting of nuclear issues related also to energy and medical
applications is to discuss radioactivity and ionizing radiation starting from young generations. Starting from
an experimental approach the students can receive a basic but correct information on radioactivity subject.
With this program students acquired awareness about environmental radioactivity, risks of inhalation of
radon and its progeny and at the same time contributed to carry out radon monitoring, participating to all the
experimental phases, from detectors preparation to data analysis.
The focus of the project is the ‘‘laboratory’’, intended as a method to ‘‘know’’ through the ‘‘know how’’, a
new way to teach and to learn. The laboratory is not only a physical place, where the students are directly
involved in experimental activities, but also a method to learn and to acquire skills in physics. So the core idea
of the project concerning the Italian secondary school is: (i) to provide the students a furnished laboratory at
their school so that they can measure the radioactivity, starting from the natural components that are a part
of our environment. In this exercise, the measurement of the 222Rn concentration is particularly well suited;
(ii) to show the different types of radiations including ionizing radiations and how they are related each to
the other; (iii) to demonstrate how ionizing radiations can be measured; (iv) to prove the fun a student can
derive from discovery and detection of ionizing radiation. Different aspects derive from this kind of project:
1. the students can approach different subjects all correlated to physics measurements, in order to understand
that their studies are not compartmentalized, but are the way to read the book of the nature;
2. to learn to present their results to the public;
3. the communication of the students involved with their family on this kind of matter;
4. allows teachers an update on matters related to modern physics;
At the last but not the least the subject allows introducing concepts related to radioprotection and more
generally on health physics.
In this paper some of the many results of this project, carried forward for 10 years, will be presented.
REFERENCES
1) G. Imme´, R. Catalano, G. Mangano, D. Morell, J. Radioanal. Chem. 299 (2014) 891.
61
4th International Nuclear Chemistry Congress I 4th-INCC 2014
NANOSTRUCTURED LIPID CARRIER DESIGN FOR IMAGING AND TARGETED
PACLITAXEL DELIVERY
Eser Uçar1, Serap Teksöz1, Çiğdem İÇHEDEF1, Perihan ÜNAK1
Ege University Institute of Nuclear Sciences, İzmir, Turkey, [email protected]
1
Nanostructured lipid carriers(NLCs) are new generation of solid lipid drug delivery systems. They have
advantages such as increased drug loading capacity, decreased drug expulsion during storage. Also suitability
of NLCs as contrast agents for gamma scintigraphyis attracting major attention.
The aim of this work is to develop nanostructured lipid carriers with imaging and active targeting functions
as a radiopharmaceutical and real time drug location imaging agent. That multifunctional drug carrier system
constituted of bioacceptable lipids. To form imperfect crystal matrix, stearic acid and oleic acid used as solid
and liquid lipids.
Folate receptors present in large numbers on cancer cells such as colon, lung, prostate, throat, brain cancers.
The use of folate derivatives can be a potential strategy for selective delivery of diagnostic and therapeutic
agents without measurable toxicity to noncancerous cells. In order to deliver insoluble anticancer drug
paclitaxel(PTX) to folate receptors a folic acid derivative Fol-PEG-CHEMS was synthesised. Tc-99m labeling
will be performed by using carbonyl aquaion [99mTc(OH2)3(CO)3]+. It is beleived that the data obtained from
this study will contribute to the future studies regarding in vivo/in vitro evaluation of radiolabeled NLCs.
REFERENCES
1) Taratula O., Kuzmov A., Shah M., Garbuzenko O.B., Minko T., 2013, Journal of Controlled Release, 171, 349-357.
2) Radtke M., Müller R.H., 2001, New Drugs, 2, 48-52.
3) Stevens P. J., Sekido M., Lee R. J., 2004, Pharmaceutical Research, 21, (12), 2153-2157.
4) Tiwari R., Pathak K., 2011, International Journal of Pharmaceutics, 415, 232-243pp.
5) Hu F.Q., Jiang S.P., Du Y.Z., Yuan H., Ye Y.Q., Zeng S., 2005, Colloids and Surfaces B: Biointerfaces, 45, 167-173.
6) Videira M.A., Botelho M.F., Santos A.C., Gouveia L.F., de Lima J.J.P., Almeida A.J., 2002, Journal of Drug Targeting, 10(8),
607-613.
7) Andreozzi E., Seo J.W., Ferrara K., Louie A., 2011, Bioconjugate Chemistry, 22, 808-818.
8) Reddy L. H., Sharma R. K., Chuttani K., Mishra A. K., Murthy R. S. R., 2005, Journal of Controlled Release, 105, 185-198.
62
session 4 - Nuclear and Radiochemistry/
Radioanalytical Chemistry
4th-INCC 2014 I 4th International Nuclear Chemistry Congress
RECOVERY OF ACTINIUM-225 AND RADIUM-223 FROM NATURAL THORIUM
IRRADIATED WITH PROTONS
Elena V. Lapshina1, Stanislav V. Ermolaev1, Boris L. Zhuikov1, Aleksandr N. Vasiliev2
Valentina S. Ostapenko2, Ramiz A. Aliev2, Stepan N. Kalmykov2
Institute for Nuclear Research Russian Academy of Sciences, 2Chemistry Department, Lomonosov Moscow State University,
Moscow, Russia, [email protected]
1
Ac and 223Ra are of considerable interest for targeted alpha-therapy of various oncology diseases due to
attractive properties of alpha-particles, namely, short range (< 100 µm) and high linear energy transfer (up
to 100 keV/µm) in biological tissue. 225Ac and 223Ra may be used either directly or as generators of the shortlived alpha-emitting radionuclides: 225Ac→213Bi and 223Ra→211Pb.
Irradiation of natural thorium with protons in the energy range 200-60 MeV can provide Ci- amounts of
both 225Ac and 223Ra1. A great number of fission and spallation products are also produced in irradiated 232Th.
The aim of this work is to develop the method of recovery of 225Ac and 223Ra from an irradiated thorium
target.
After dissolution in 6M HNO3 with the addition of catalytic amounts of HF, thorium was removed by liquid
extraction. Tributyl phosphate (TBP) and di(2-ethylhexyl) ortho-phosphoric acid (HDEHP) were studied as
extracting agents.
Aqueous phase containing 225Ac and 223Ra was processed with extraction-chromatographic resins (TrisKem
Company) and cation exchange resin AG 50×8 (BioRad Company). DGA resin (N, N, N’, N’ tetroctyldiglicolamide) was used for separation of 225Ac from 223Ra. Actinium was adsorbed from 6M HNO3 solution,
whereas radium passed through. Then actinium was stripped off with 0.01 M HNO3 solution together with
lanthanides and traces of some other radioimpurities. The purification of actinium fraction was performed
with TRU resin (octylphenyl-N,N-di-isobutyl carbomoylphosphine oxide). For 225Ac, a chemical yield up to
85% was achieved, and the radionuclidic purity was ≥ 99.5%.
223
Ra was recovered from the DGA eluate in two steps. First it was separated from alkaline elements, as well
as Ru and Ag, using AG 50×8. The final isolation of radium from other alkali-earth elements was performed
with Sr-resin (4,4’(5’)-di-t-butylcyclohexano-18-crown-6).
Essential part of 223Ra was also accumulated by 227Th decay (organic phase) during ~ 3 weeks after extraction.
The re-extraction of radium with HCl and HNO3 solutions was studied in a wide range of acid concentration.
Then the solution was conditioned, and 223Ra was recovered with AG 50×8 and Sr resin as above. The total
chemical yield of 223Ra was ~ 80%, radionuclidic purity ≥ 99%.
225
REFERENCE
1)S. V. Ermolaev, B. L. Zhuikov, V. M. Kokhanyuk, V. L. Matushko, S. N. Kalmykov, R. A. Aliev, I. G. Tananaev and B. F.
Myasoedov, Radiochim. Acta. 100 (2012) 223.
65
4th International Nuclear Chemistry Congress I 4th-INCC 2014
Prodcution of 99Mo/99mTc generator using high specific activity of
99
Mo recoiled out from molybdenum nanoparticles target by the
100
Mo(n,2n)99Mo reaction
Yuichi Hatsukawa1, K. Tsukada1, K. Hashimoto1, T. Sato1, M. Asai1, N. Sato1, A.
Toyoshima1
Japan Atomic Energy Agency, Tokai, Japan, [email protected]
1
We propose a 99Mo production project via the 100Mo(n,2n)99Mo reaction using fast neutrons (E>10MeV) from
accelerator(1,2). Only low specific radioactive 99Mo, however, can be obtained in this method. Although
labeled technetium compounds would be available by this method, a compact technetium generator is
still required in medical facilities. The purpose of this study is to investigate about production of high
specific radioactivity of 99Mo and 99Mo/99mTc compact generator using and the 100Mo(n,2n)99Mo reaction
with nanoparticle molybdenum target. In the fast neutron reaction with nanoparticle molybdenum targets, a
certain amount of 99Mo ions are expected to be recoiled out from the target and isolated.
As neutron irradiation target, molybdenum nanoparticles (APS;70 nm) were prepared by grinding with
potassium chloride (KCl) powder, then pressed into a 10mm diameter disk. About 950 mg of the Mo/KCl
target which contained about 500 mg molybdenum nanoparticles were irradiated with accelerator neutrons
for 6 hours. After neutron irradiation, the Mo/KCl target was dissolved in pure water, then solution and
molybdenum nanoparticles were separated by centrifuge method. The solution contained recoiled 99Mo ion
by fast neutron reactions was poured into alumina column. 1-7 % of 99Mo produced in the Mo/KCl target was
absorbed onto the alumina column. The 99mTc was obtained by pouring saline solution through the alumina
column of immobilized 99Mo. This result shows possibility for the 99Mo/99mTc generator system production
using high specific activity of 99Mo recoil out from nanoparticle Mo target with the 100Mo(n,2n)99Mo reaction.
Enrichment factor of this system and neutron energy dependency of yields of high specific activity of 99Mo
will be discussed.
REFERENCES
1) Y. Nagai and Y. Hatsukawa, J. Phys. Soc. Jpn, 78 (2009) 033201
2) Y. Nagai et al., J. Phys. Soc. Jpn, 82 (2013) 064201
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4th-INCC 2014 I 4th International Nuclear Chemistry Congress
SEPARATION OF 225Ac FROM RARE EARTH ELEMENTS GENERATED BY PROTON
IRRADIATION OF NATURAL THORIUM
Valentina S. OSTAPENKO1, Aleksandr N.Vasiliev1, Elena V. Lapshina2, Stanislav V.
Ermolaev2, Ramiz A. Aliev1, Stepan N. Kalmykov1, Boris L. Zhuikov2
Chemistry Department, Lomonosov Moscow State University, 2Institute for Nuclear Research Russian Academy of Sciences,
Moscow, Russia, [email protected]
1
Alpha-particle therapy (using Ac-225 and its daughter product Bi-213) is a new and promising treatment for
many forms of cancer.
α-emitter 225Ac may be produced from natural thorium irradiated with protons in the energy range 200-60
MeV.
The irradiated thorium was dissolved in 6M HNO3 with the addition of HF. Although the radionuclide
composition of the irradiated target comprises several tens of various elements, the main difficulties was to
separate Ac from Th and rare earth elements especially La and Ce. Thorium was extracted by di(2-ethylhexyl)orthophosphoric acid [HDEHP] with toluene (1:1). For radiochemical separation of Ac from rare
earth elements we used extraction chromatography sorbents produced by TrisKem company: DGA (N,N,N
`,N`tetroctyldiglicolamide), and TRU (octylphenyl-N,N-di-isobutyl carbomoylphosphine oxide).
DGA resin have a steep dependence of k’ for trivalent ions on HNO3 concentration. k’ (DGA) reaches
maximum in 6-7 M HNO3 solution and drops down to 1-2 in 10-2 M HNO3 solution [1]. We used these
resin to adsorb actinium and rare earth elements from HNO3 solution of favorable acidity, while mono- and
divalent ions (Cs+, Ra2+, Ba2+, Sr2+) as well as most of Ru, Zr, Nb, and others were washed out of the column.
TRU resin displays a moderate k’ values ~102 for trivalent ions in the range of 1-5 M HNO3 [2]. Optimization
of acidity and column length allowed us to separate actinium from lanthanides.
Thus, the actinium isolation comprises three main steps: 1) separation from macro-amounts of thorium;
2) pre-concentration and separation of the fraction containing actinium and rare earth elements from other
elements; 3) separation of actinium from rare earth elements.
Chemical yield of the obtained 225Ac fraction was not less than 85% and radionuclidic purity of final
product was better than 99.5%.
REFERENCES
1)D.R. McAlister., E.P. Horwitz, Solvent Extraction and Ion Exchange, 2007, V.25, P.757-769.
2)E.P. Horwitz, D.R. McAlister, A.H. Bond, R.E. Barrans, Solvent Extraction and Ion Exchange, 2005, V.23, P.319-344.
67
session 5 - Nuclear and Related Techniques
4th-INCC 2014 I 4th International Nuclear Chemistry Congress
Evaluation of Westcott g(Tn)-factors for k0-NAA using non-1/v
nuclides
Robbert van Sluijs1, Radojko Jacimovic2, Attila Stopic3
k0-ware, 2Department of Environmental Sciences, Jozef Stefan Institute, 3Centre for Nuclear Applications, Australian Nuclear
Science and Technology Organisation, Heerlen, Netherlands, [email protected]
1
The Westcott convention was introduced in the early 1990’s in k0-NAA. This convention introduced a g(Tn)factor that is dependent on the neutron temperature and allows for the analysis of nuclides whose thermal
neutron capture cross-sections do not follow the 1/v law, so called non-1/v nuclides.
The most commonly used Høgdahl convention is not able to evaluate these nuclides accurately.
The recently proposed ‘extended’ Høgdahl convention simply introduces the g(Tn)-factor for the activation
caused by the thermal neutron fraction as defined in the k0-method. This allows the strongest non-1/v nuclides
like Lu-176, Eu-152(m) and Yb-169 to be measured with an analytically acceptable accuracy without the
use of extra calibrations.
This paper reviews old g(Tn)-factors used for the determination of k0-values, for the strongest non-1/v
nuclides. These factors are compared to recently published factors as well as factors that can be calculated
using the reference nuclear capture ENDF-database. Additionally g(Tn)’s for all k0-nuclides are reviewed.
71
4th International Nuclear Chemistry Congress I 4th-INCC 2014
LEAD ISOTOPIC RATIOS IN ENVIRONMENTAL SAMPLES AS ORIGIN MARKERS
Alberto Fernández Alarcón1, Trinidad Martínez Castillo1, Graciela Zarazua Ortega2,
Samuel Tejeda Vega2, Pedro Ávila Pérez2
Facultad de Química, Edificio D, Universidad Nacional Autónoma de México, 2Instituto Nacional de Investigaciones Nucleares,
México, Mexico, [email protected]
1
Lead is the most studied heavy metal due to it is known toxicity1. Some sources of anthropogenic lead
pollution are: sequel of mining, foundry, industrial activities and so antique leaded-gasoline. The last one has
a great importance in urban zones with high vehicular traffic. In Mexico City, a decrease on lead emission
has been observed as a result of the change to low leaded-gasoline. In 1986 the mean of lead emission was
1421 ton/year and for 1995 the lead emission diminished to 109 ton/year. In 1996 the lead-free gasoline was
introduced and a stricter regulation of car emission was implemented, before all this, lead is still present
in several environmental samples2. In order to identify the source, with the most contribution in the lead
pollution in environmental samples from the Metropolitan Zone of Toluca Valley (MZTV), a comparative
studied, between the isotopic ratios of the stables isotopes of lead (204Pb, 206Pb, 207Pb, 208Pb), was realized
in a group of five referents of source of lead pollution (gasoline, diesel, coat, potable water and pellets of
industrial lead) and in a group of environmental samples (mosses, soils, street dust and aerosols). After an
acid digestion with ultra-pure reagents, the samples were measured in ICP-Ms. The result´s quality was
proved with a reference material of common lead (NIST 981). Consecutive statistical analysis show that the
most important sources of lead, in mosses and soils, are the industrial activity and the natural process; while
the gasoline has a significant participation in the present of lead in the aerosols and dust samples. Others
facts like the contribution of the atmospheric conditions in the process of lead distribution were verified too,
the mosses samples were collected in two seasons of the year: dry-cold season (winter) and wet-hot season
(summer)3. The statistical analysis, between the soils samples and both seasons sampling of mosses, show a
little bit more significant differences with the dry-cold season sampling.
REFERENCES
1) Nriagu J.O.. Science. 272, (1996) 223-224
2) T. Martínez, J. Lartigue, F. Juárez, P. Avila-Perez, G. Zarazua, C. Marquez. M.P. Orta, V. Alvarez. Journal of Atmospheric
Chemistry. 49, (2004) 415-424
3) G. Zarazúa, P. Ávila- Pérez, S. Tejeda, T. Martínez, J. Poblano- Bata, C. Zepeda, H. Ortiz-Ontiveros, G. Macedo. J. SánchezMeza. Scientific World Journal. Article ID 426492 (2013).
72
4th-INCC 2014 I 4th International Nuclear Chemistry Congress
Assessing total potassium in forest soils by measuring 40K
Márcio Arruda Bacchi1, Felipe A. Biguzzi1, Elisabete A. De Nadai Fernandes1, André Luis
Lima de Araújo1
Center for Nuclear Energy in Agriculture, Piracicaba, Brazil, [email protected]
1
The natural radionuclide 40K has long been applied for assessing the content of total potassium in diverse
types of samples. There are several successful examples of such application in literature, which include
the pioneer analysis of liquid fertilizers1 and a recent publication2 comprising the analysis of several
biological certified reference materials. The assessment of total potassium by measuring 40K with gammaray spectrometry has the potential to be a fast non-destructive method, capable of analyzing kilogram-size
samples, which can be especially advantageous when dealing with heterogeneous materials. Moreover, the
method completely fulfill the green chemistry requirements, since there is no need of chemicals for sample
preparation and it only involves the natural radioactivity of the material being analyzed. However, a huge
variation of the isotopic abundance of 40K (from 0.004% to 0.013%) was recently reported for forest soils
under different environmental conditions.3 Considering such variation, the use of 40K for assessing the total
potassium content in soils would not be possible, since results could present unacceptable and unpredictable
bias. Here, samples of forest soils collected in São Paulo State, Brazil, were dried, milled and measured by
gamma-ray spectrometry for determining 40K. Portions of 30 g of each sample were inserted into plastic
containers and counted for 12 h directly on the endcap of a HPGe detector with 50% relative efficiency
at the 1332 keV photopeak of 60Co. A soil reference material (IAEA-327) with certified value for 40K was
added to the analytical series for quality control. Standard solutions prepared from potassium acetate at
various concentrations were measured in the same conditions of samples for assessing the total content of
potassium. A perfect agreement was observed between data obtained from gamma-ray spectrometry (40K)
and data previously provided by INAA (41K activated to 42K), comprising eighteen samples of superficial
soil (up to 40 cm depth) collected from three different areas. The typical expanded uncertainty of 40K results
was 10%, which is suitable for most analysis of soil. Therefore, at the conditions of this study, the isotopic
variation recently reported3 was not observed, and the assessment of total potassium by measuring 40K was
possible. Aiming at further improving the analytical procedure, 2 kg soil samples were dried and directly
analyzed in Marinelli beakers, without any other treatment. The large samples provided a slight reduction
of uncertainties, even using a shorter counting time (about one hour), combined with a very easy and fast
sample preparation.
REFERENCES
1)W. G. Harris, W. V. Kessler, J. E. Christian, E. D. Schall, J. Agric. and Food Chem. 12 (1964) 144.
2)M. Maiti, A. Mandal, S. Lahiri, Appl. Radiat. Isotopes 71 (2013) 37.
3)R. Fujiyoshi, N. Takekoshi, K. Okamoto, J Radioanal Nucl Chem 299 (2014) 1365.
73
session 6 - Radiation Chemistry
4th-INCC 2014 I 4th International Nuclear Chemistry Congress
LIXIVIATION OF METALS IN COLUMNS OF TROPICAL SOIL AMENDED WITH
PHOSPHOGYPSUM
Marcelo Bessa Nisti1, Cátia Heloisa Rosignoli Saueia1, BARBARA P. MAZZILLI1
Laboratório de Radiometria Ambiental, Instituto de Pesquisas Energéticas e Nucleares (IPEN), São Paulo, Brazil,
[email protected]
1
The Brazilian phosphate fertilizer is obtained by wet reaction of the igneous phosphate rock with concentrated
sulphuric acid, giving as final product, phosphoric acid, and dehydrated calcium sulphate (phosphogypsumPG) as a by-product. PG presents in its composition metals originally present in the phosphate rock used as
raw material. The main phosphate industries in Brazil are responsible for the production of 5.5x106 metric
tons of phosphogypsum annually, which is stored in stacks. The level of impurities present in phosphogypsum
makes its disposal or reutilization an environmental concern. This PG has been used for many years in
agriculture as a soil amendment. For its safe long-term application, it is necessary to characterize the
impurities present in PG. This study is important since such impurities can migrate to agricultural products
and food chain or contaminate the water. The concentration of metals (As, Cd, Cr, Hg, Ni, Pb and Se)
in fertilizers and soil conditioners are controlled by national agriculture regulation agency Ministério da
Agricultura, Pecuária e Abastecimento. The State Environmental Agency, Companhia Ambiental do Estado
de São Paulo established also reference values for soil quality for the following elements As, Cd, Co, Cr,
Cu, Hg, Ni, Pb, Se and Zn. Several papers were published concerning the characterization of heavy metals
in Brazilian PG and fertilizers. The main objectives of this paper is to study the availability of As and metals
(Cd, Cr, Ni, Se, Hg and Pb) present in the Brazilian phosphogypsum used in agriculture. For this purpose, an
experiment was conducted in the laboratory, in which, columns were filled with Brazilian typical sandy and
clayish soils and phosphogypsum and were percolated with water, in order to achieve a mild extraction of
these elements. The volume of water to be percolated was based in the average rainfall of the study area. The
availability of the metals was evaluated by measuring the total concentration in the soil + phosphogypsum
and the concentration in the leachate, in order to establish the ratio between the total fraction and the
available one. The clayish soil presented concentration of the elements As, Cd, Cr, Ni, Pb higher than the
sandy soil. It was concluded that the addition of PG to the soils, even in quantities that exceeded 10 times
the amount of phosphogypsum necessary to achieve the base saturation of the soils, does not contribute to
an enhancement of the metals content in water.
77
4th International Nuclear Chemistry Congress I 4th-INCC 2014
Radiolytic decomposition of environmentally persistant
perfluorinated surfactants with the use of ionizing radiation
Marek Trojanowicz1,2, Anna Bojanowska-Czajka2, Krzysztof Bobrowski2, Gabriel
Kciuk2, Monika Lyczko2
Department of Chemistry, University of Warsaw, 2Institute of Nuclear Chemistry and Technology - Dorodna, Warsaw, Poland,
[email protected]
1
Perfluorinated surfactants (PFSs), in which in alkyl chains all hydrogen atoms are substituted with fluorines,
are industrially produced since 1950-ties. Their particular properties such as high surface tension activity
and outstanding chemical stability are main reasons of broad applications. They include impregnation of
paper and textiles, application as components of a fire fighting foams and lubricants. Wide interest in their
environmental role since beginning of 2000-ties resulted from discovery of a common global presence of
those anthropogenic compounds, mostly perfluorinated sulfonates and carboxylates, in human and animal
organisms, and in the environment, even in the most remote places1. It resulted in wide development of
analytical methods of their determination 2, as well as toxicological studies3.
The extraordinary chemical stability of PFSs results in insufficient efficiency of their removal from wastes,
surface waters, and raw and drinking water sources by conventional treatment processes. This implies
increasing interest in search of new treatment technologies. They include both methods based on reductive
dehalogenation (employing e.g. sub-critical elemental iron reduction or UV-iodide photolysis)4, as well
as advanced oxidation processes (AOPs)5. The pulse radiolysis measurements indicated, that reactions of
perfluorinated octanoic acid (PFOA) or perfluorinated octanesulfonic acid (PFOS) with •OH radical and
hydrated electron eaq- exhibit similar kinetics. Then this implies a possibility of favorable application for this
purpose of an ionizing radiation gamma or accelerated electron beam, where as a result of water radiolysis
strong reactants - oxidizing •OH radicals and reducing hydrated electrons are formed in similar amounts.
The obtained rate constants are 2-3 orders of magnitude lower compared to reactions of other different
organic pollutants. This confirms high chemical resistance of examined PFSs.
The identification of degradation products of PFOA and PFOS was carried out using LC-MS and GC-MS
methods, while the yield of defluorination was determined using ion-chromatography with conductivity
detection. Studies on radiolytic decomposition of PFCs were carried out in aqueous solutions with initial
concentrations 1 mg/L by gamma and EB irradiation, and also by hyphenated processes combining radiation
with additional chemical processes enhancing the yield of radical formation. The products of decomposition
in function of absorbed dose are fluoride and PFSc with shorter alkyl chains, than irradiated species.
REFERENCES
1) K. Prevedouros, I. T. Cousins, R. C. Buck, S. H. Korzeniowski, Environ. Sci. Technol. 40 (2006) 32.
2) M. Trojanowicz, M. Koc, Microchim. Acta 180 (2013) 957.
3) C. Lau, K. Asnitole, C. Hodes, D. Lai, A. Pfahles-Hutchens, J. Seed, Toxicol. Sci. 99 (2007) 366.
4) C. D. Vecitis, H. Park, J. Cheng, B. T. Mader, M. R. Hoffmann, Front. Environ. Sci. Engin. China 3 (2009) 129.
5) H. F. Schröder, R. J. W. Meesteres, J. Chromatogr. A 1082 (2005) 110.
78
4th-INCC 2014 I 4th International Nuclear Chemistry Congress
BUILDING A NUCLEAR FORENSIC ANALYSIS CAPABILITY IN BRAZIL
Jorge Eduardo de Souza Sarkis1, Danniele Scarpin Rosa1, Ana Lucia Exner GODOY1, Demerval
Leonidas RODRIGUES1, Elita Fontenele Urano de CARVALHO1, José Roberto Martinelli1,
Marycel Elena Barboza Cotrim1, Nelson Batista Lima1, Osvaldo Negrini Neto2, Marcio
Talhavine3
Instituto de Pesquisas Energéticas e Nucleares, 2Instituto de Criminalistica do Estado de São Paulo, 3Departamento de Polícia
Federal, São Paulo, Brazil, [email protected]
1
Since nuclear energy was first utilized, the risk related with criminal or unauthorized acts involving nuclear
or other radioactive (RN) materials have been a serious concern for the entire global nuclear community.
During the last decades, the possibility that terrorists or other criminals might obtain RN materials for
malicious use has become a real threat to global security especially after the collapse of the Soviet Union,
at the end of the 1980’s, when several tons of these materials were stolen. Once illicit nuclear or other
radioactive material is detected , a response plan have to be auctioned safely and within an acceptable time
frame. An important element of the response plan is the nuclear forensics investigation of the intercepted
material. Nuclear forensics investigation involves the collection and analysis of classical and nuclear
evidences in the crime scene and requires a number of chemical , physical and nuclear analysis to be
performed by experienced , and well trained , laboratories and experts . This paper will describe the efforts,
actions and results , during the process to establish in Brazil a Nuclear Forensics Laboratory Network.
79
4th International Nuclear Chemistry Congress I 4th-INCC 2014
RADIATION EFFECTS IN PA6/EPDM BLENDS
Traian Zaharescu1, Marius Eduard Lungulescu1, Alina Ruxandra Caramitu1, Virgil
Marinescu1
INCDIE ICPE CA, Department of Advanced Materials, Bucharest, Romania, [email protected]
1
The modifications in the stability of polyamide 6 (PA6)/ethylene-propylene diene copolymer (EPDM) were
studied by isothermal and nonisothermal chemiluminescence, FT-IR spectroscopy. The compositions of
blends consists of PA 6 as basic component and EPDM at different loadings (0, 10, 20 and 30 wt%). The
exposure to gamma-radiation (137Cs) was performed in air at room temperatures at five total doses: 10,
25, 50, 100 and 160 kGy dose rate being 0.4 kGy.h-1. The oxidation takes place with different rates as the
function of elastomer concentration. The maximum CL intensities attained at 210 oC corresponds to highest
oxidation rates in nonisothermal CL spectra. The delay of oxidation due to the presence of elastomer can be
noticed in the nonisothermal CL intensities of all compositions. The isothermal CL determinations reveal
the contribution of elastomer to the oxidative strengths of PA 6/EPDM compounds (Fig. 1).
The spectra recorded by ATR-FTIR technique show structural modifications proved the diminution in 3296,
3080, 1636 and 1540 cm-1 bands belonging to amino groups and the intensification in 2923, 2852 and 1459
cm-1 bands from polyolefin fraction.
Fig. 1. Isothermal CL spectra of two PA6/EPDM blends exposed to (a) 0kGy and (b) 50 kGy (£) 100/0;
(¯) 90/10; () 80/20; (r) 70/30.
The SEM investigations on irradiated neat and PA6/EPDM 70:30 samples have pointed out the texture
modifications in the bulk of materials in the regions of elastomer (Fig. 2).
(a) PA 6
Fig. 2. SEM photos on after their exposure to 100 kGy
80
(b)PA6/EPDM (80/20)
session 7 - Nuclear Reactors/
Radioecological and Geochemistry
4th-INCC 2014 I 4th International Nuclear Chemistry Congress
TRANSFER OF URANIUM AND RADIUM TO CHINESE CABBAGE FROM SOIL
CONTAINING ELEVATED LEVELS OF NATURAL RADIONUCLIDES
Borut SMODIŠ1, Marko ČERNE1
Jožef Stefan Institute, Ljubljana, Slovenia, [email protected]
1
Environmental contamination by Naturally Occurring Radioactive Material (NORM) is a common
phenomenon in uranium mining and milling areas. Disposal of uranium ore processing materials may result
in soil contamination if inappropriate waste remediation is applied. Radionuclides retained in the soil by soil
colloids may be subsequently taken up by plants. The uptake process depends mainly on concentration of
the radionuclides in soil, soil properties and physicochemical conditions and microbial activity of soil. Some
Brassica plants are known to have the ability of accumulating radionuclides in the shoots in higher quantities
from the NORM-contaminated soil. In the present study, transfer of radium and uranium to Chinese cabbage
(Brassica pekinensis Rupr.) from soils contaminated with uranium-mill tailings (UMT) was investigated.
A laboratory-based study was carried out as a field experiment may exhibit high transfer factor variability
related to substantial influence of uncontrolled plant growing and climate conditions. In the study different
contamination scenarios were applied within a pot experiment designed to evaluate transfer of radium and
uranium to Chinese cabbage from the UMT-contaminated soil. Radionuclides were assayed in the aboveground organs to calculate the plant-to-soil radionuclide concentration ratios for various levels of soil
contamination. Preliminary results of 118.3 ± 6.3 and 562 ± 28 Bq kg-1 dry mass for radium in cabbage
leaves at 20 and 60 % of UMT content in soil, respectively, and 1.0 ± 0.2 and 3.6 ± 0.6 Bq kg-1 dry mass
for uranium in cabbage leaves at 20 and 60 % of UMT content in soil, respectively, showed increased
accumulation of radium in cabbage shoots on more contaminated soil and lower accumulation of uranium. In
the presentation, data for different levels of contamination under various growing conditions are shown and
discussed. Measurement results are presented and the radionuclide concentration ratios critically evaluated.
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
KINETICS SORPTION OF METAL RADIOTRACERS IN THE WATER-SEDIMENT
INTERFACE OF A HIGHLY CONTAMINATED COASTAL AREA (SEPETIBA BAY, RIO
DE JANEIRO, BRAZIL)
Melissa Nogueira Sondermann1, Katia Noriko Suzuki1, Mirian Araujo Carlos Crapez2,
Sambasiva Rao Patchineelam1, Luis Fernando Bellido3, Ricardo Tadeu Lopes4, Alfredo
Victor Bernedo Bellido1
Departamento de Geoquímica, Universidade Federal Fluminense (UFF), 2Programa de Pós-Graduação em Biologia Marinha,
Universidade Federal Fluminense, 3Instituto de Radioproteção e Dosimetria (IRD/CNEN), 4Laboratório de Instrumentação
Nuclear, Universidade Federal do Rio de Janeiro, Niterói, Brazil, [email protected]
1
This study evaluated the removal kinetics of Zn and Cd from tidal water to creek sediments in a highly
contaminated area in Sepetiba Bay, RJ. Radiotracer experiments with mangrove sediment columns have
showed the efficiency of metal removal from the water column to the underlying sediment1. The function of
bacterial biofilm as an environmental compartment that retain trace metals in the sediment-water interface
can be applied to amplify the metal removal capacity of marine water. This study aimed to evaluate the
removal kinetics of metals (Zn and Cd) in the sediment-water interface and the bacterial biofilm role
in determining this removal by using radiotracer (65Zn and 109Cd) experiments2. For this study, benthic
bacteria with Cd and Zn resistance were cultivated in the Laboratory of Bacterial Ecology (UFF), exposed
to different concentrations of Cd and Zn (artificial biofilm). Twelve sediment cores (40 cm) and tidal water
were sampled in a fringe mangrove forest in Madeira Island (22°55’11.0’’S, 43°49’05.98’’ W), located in
Sepetiba Bay, Rio de Janeiro. Four cores were inoculated with 4 mL of this artificial biofilm in the sediment
surface. Two of these cores and tree others with natural biofilm were submitted to a formaldehyde solution
treatment before the addition of radiotracer-spiked water, to evaluate the effect of biological activity on the
sediment sorption capacity, by comparing biocide-treated with control cores. The experiment lasted for 48h
and water samples were taken at regular intervals to measure the activity of radiotracers 65Zn and 109Cd. The
determination of radiotracers activities in water samples were performed by gamma-ray spectroscopy with
a high-purity (HPGe) detector, using the Genie 2000 software for this analysis. Preliminary results (without
biofilm treatment) showed first order kinetics removal from water with two different half-live times (t1/2).
The average first t1/2 was higher for Zn (4.18± 1.28 h) than for Cd (3.05± 0.82 h), while the average second
t1/2 was 16.12±1.52 h for Cd and 16.0± 1.68 h for Zn. The first half-live removal kinetics of metals in biofilm
cores was higher for Zn (3.44± 0.85h) than for Cd (2.33± 0.23h) as well as the second t1/2 (Zn 17.45± 3.68h
and Cd 17.37± 0.74h). Furthermore, the t1/2 in formaldehyde-treated cores was consistently longer when
compared with other cores. The average first t1/2 was for Cd 6.15±1.33h and for Zn 12.7 ± 4.3h, while the
average second t1/2 was for Cd 23.4± 5.46h and for Zn 29.01± 5.77h.
REFERENCES
1) E. C. Machado et al. J. Radioanal. and Nucl. Chem. 249(2001) 653-656.
2) K. N. Suzuki et al. Mar. Environ. Res. 83(2013) 96-100.
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4th-INCC 2014 I 4th International Nuclear Chemistry Congress
RADIOGRAPHY APLLIED TO FUNERAL AND UTILITY ARCHAEOLOGICAL
CERAMICS STUDIES
Alfredo Victor Bellido Bernedo1, Rose M. LATINI1, Maria Inês S. SOUZA2, Gevaldo L. ALMEIDA2
Instituto de Química. Universidade Federal Fluminense, 2Instituto de Engenharia Nuclear, Rio de Janeiro, Brazil,
[email protected]
1
The aim of this study is to investigate manufacturing techniques used in prehistoric Brazilian pottery from
Amazon Basin in the state of Acre and Region of Lakes in the state of Rio de Janeiro using Gama Ray
Radiography. Previous studies show that the difference between the manufacturing techniques - palette and
rollers - is better identified by radiography using low energy γ-rays. For this purpose, radiographic images of
funeral and utility ceramics were obtained with a system comprised of a source of γ-rays from 165Dy (95 keV)
and Imaging Plate as detector. The 165Dy source was produced at Argonauta research reactor of the Instituto
de Engenharia Nuclear - IEN/CNEN. The radiographic images using γ-rays from 165Dy have been acquired
under an exposure time of a couple of hours. After acquisition, the images have undergone a treatment to
improve their quality through the enhancement of their contrast, a procedure involving corrections of the
beam divergence, sample shape and averaging of the attenuation map profile. Preliminary results show
difference between the ceramics studied and complement the characterization and classification studies of
pottery based on trace chemical elements composition.
REFERENCES
1) R.M. Latini, M. I. S. Souza, G. L. Almeida and A.V.B. Bellido. Manufacturing Techniques Studies of Ceramics by Neutron
and γ-Ray Radiography. XXXVI Reunião de Trabalho de Física Nuclear no Brasil. (2013).
2)A Lindahl and I. Pikirayyi. Ceramics and change: an overview of pottery production techniques in northern South Africa and
eastern Zimbabwe during the first and second millennium. Archaeol Anthropol Sci, 2 (2010) 133–149.
3) R.M. Latini, A.V. Bellido, U. M. Vinagre Filho, M. I. S. Souza, I. Lima, D.F. Oliveira and R.T.Lopes, Archaeometric studies
by neutron, x-ray radiography and microCT. AIP Conf. Proc. 1529 (2013) 49.
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
BIOAVAILABILITY OF TRACE METALS IN SEDIMENTS: A REVIEW
Vivianne Lúcia Bormann de Souza1, Rafaela E. A. V. RODRIGUES1, Waldecy A. SILVA1, Clovis A.
HAZIN1
CNEN/CRCN, Recife, Brazil, [email protected]
1
The chemical association of metal species in sediments provides indications about the release of trace metals
by physics, chemical and biological processes, with toxic effects under certain environmental conditions.
The knowledge of the way those metals are bond to sediments, serves to recognize specific sources of
pollution in the aquatic system. Speciation plays an important role as far as bioavailability and toxicity are
concerned. It must be noted that although the bioavailability of metals is related to geochemical phase in
which these metals are, the effective bioavailability for plants and animals will depend on the prevailing
environmental conditions which may or may not make them available to the environment. As a result, a
metal can have the same concentration in different sediments and present toxicity in only one of them,
showing that the toxicity is dependent on the bioavailability of contaminants. Although the sediment may
have been contaminated at a certain time, the metal accumulated in it may be considered a contaminant,
only if the chemical form in which it is can characterize it as such. The accumulation of metal particles in
sediments occur by the following mechanisms: a) adsorption to the material fine particles; b) precipitation
of the element in the form of compounds (carbonates, sulfates or oxides); c) co-precipitation of the element
with iron and manganese oxides; d) complexation with the organic matter; e) incorporation into the crystal
lattice of minerals (silicates). Currently, five phases are considered when studying the bioavailability of trace
elements in sediments: a) exchangeable phase, using MgCl2 (causes change in salinity); b) leachable phase,
with acetic acid (causes pH change); c) reducible phase, using hydroxylamine hydrochloride (allowing the
release of metals bound to oxy-hydroxides of Fe and Mn); d) oxidizable phase with hydrogen peroxide
(causes the degradation of organic matter); e) pseudo-residual phase, using aqua regia (allows the release of
metals associated with minerals). In 1986, some authors, found that Cu and Cr were, preferentially, bound
to Fe and Mn oxides, except in soils with high organic matter content; while Pb and Cd appeared in the
most bioavailable forms (exchangeable and leachable). During 1997, others, performing the fractionation
of metals in soil with steel waste, found that all metals were in the less bioavailable forms, and Ni, Cd and
Cu were found in the pseudo-residual phase. According to works performed in 2007, Co and Ni are usually
found in the residual phase; these metals were found in smaller proportions in the oxidizable fraction and Cu
was found mainly in the oxidizable phase. Fractionating Ni in soil effluents, others studies demonstrated that
this metal added to the soil was retained in leachable and reducible fractions, while the Ni added by biosolids
was extracted in the exchangeable fraction. According to Lima et al. (2014), Cu was found, mainly, at the
oxidized phase and Fe and Mn in the exchangeable phase; either, Lima et al. (2014) found Zn and Pb in the
reducible phase. In 2000, others researchers, had found Zn in reducible and pseudo-residual phases, being
Cu and Ni found in the pseudo-residual phase. And Ni and Co were also measured in the oxidizable phase.
In conclusion, the first three phases are considered the most bioavailable. In the last two fractions, metals
are strongly bound to the sediment constituents and are not available for animals and plants. Metals present
in the organic phase are, only, removed by strong oxidizing conditions, releasing the metal in soluble form.
The metals contained in the pseudo-residual phase measure the degree of environmental pollution, since a
large amount of metals present in this phase indicates a lower degree of pollution.
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session 8 - Nuclear and Related Techniques
4th-INCC 2014 I 4th International Nuclear Chemistry Congress
MULTIELEMENT ANALYSIS OF LICHEN SAMPLES USING XRF METHODS.
COMPARISON WITH ICP-AES AND FAAS
Zahily Herrero Fernández1, Juan Reinaldo Estevez ÁLVAREZ1, Alfredo Montero ÁLVAREZ1,
Iván Pupo GONZÁLEZ1, José Araújo dos Santos JÚNIOR2, Marvic Ortueta MILAN1, Guillermo
Mesa PÉREZ1, Dennys Leyva BOMBUSE1, Maydel Rodríguez GONZÁLEZ1, Débora hernaández
TORRES1, Nelis Blanco HERNÁNDEZ3, Román Padilla ÁLVAREZ1,4
Centre for Technological Applications and Nuclear Development (CEADEN), 2Federal University of Pernambuco, 3Institute of
Ecology and Systematic (IES), 4International Atomic Energy Agency (IAEA), La Havana, Cuba, [email protected]
1
This paper presents the results of the analysis of Ca, Fe, Zn, Br, Rb, Sr and Pb in lichen samples used as
biomonitors of air pollution collecting in Havana in 2009 and 2010. It was also made a statistical comparison
between these results and the previous ones that was obtained during a first campaign made in 2004. Two
different X-Ray Fluorescence (XRF) methods were used, employing for excitation an annular 109Cd source
and a Mo X-ray tube with a molybdenum secondary target. In both cases, matrix effects were corrected by
the use of normalization for the Compton scattered peak. The quantification was performed using calibration
curves made by measuring biological Certified Reference Materials (CRM). XRF results were corroborated
by comparing with the results obtained by Inductively Coupled Plasma-Atomic Emission Spectrometry
(ICP-AES) and Flame Atomic Absorption Spectrophotometry (FAAS). The quality of the analytical results
of the ICP-AES and FAAS was evaluated analyzing biological CRMs. No significant differences were
found between the different techniques. The mass fractions of the elements analyzed in the lichen samples
collected in 2004, 2009 and 2010 were similar. The elemental distribution patterns obtained for each metal
were associated with different pollution sources.
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
CHALLENGES IN THE QUALITY ASSURANCE OF ELEMENTAL AND ISOTOPIC
ANALYSES IN THE NUCLEAR DOMAIN BENEFITTING FROM HIGH RESOLUTION
ICP-OES AND SECTOR FIELD ICP-MS
Michael Krachler1, Rafael ALVAREZ-SARANDES-LAVANDERA1, Paul CARBOL1, Rikard
Malmbeck1, Pavel SOUČEK1, Stefaan Van Winckel1
European Commission - Joint Research Centre, Institute for Transuranium Elements, Karlsruhe, Germany, michael.krachler@
ec.europa.eu
1
Accurate analytical data reinforces fundamentally the meaningfulness of nuclear fuel performance
assessments and nuclear waste characterization. Regularly lacking matrix-matched certified reference
materials, quality assurance of elemental and isotopic analysis of nuclear materials remains a challenging
endeavour. Consequently, complementary analysis employing diverse instrumental techniques based
on different physical detection principles is a key issue especially when “non-separated” fuel solutions
containing all fission products as well as actinides are to be analysed.
In this context, this study highlights various dedicated experimental approaches envisaged at the European
Commission – Joint Research Centre – Institute for Transuranium Elements, mainly focussing on the use
of high resolution ICP-OES and sector field (SF-)ICP-MS. However, also a- and g-spectrometry served
to characterise extensively the investigated actinide solutions for their actual concentration, thinkable
impurities and isotopic purity. Using a commercial high resolution ICP-OES spectrometer, sensitive emission
wavelengths for potential isotopic and elemental analysis of nuclear samples were identified and inspected
thoroughly. Besides, analytical procedures based on SF-ICP-MS were developed and applied subsequently
to cross-validate the ICP-OES results. The benefits and pitfalls of different calibration strategies applied to
ICP-OES and SF-ICP-MS analysis were examined carefully.
Specific innovative examples presented here include 1) U isotopic analysis employing high resolution ICPOES, identifying depleted, natural and enriched (at various levels) abundances of 235U; 2) the accurate
determination of alkaline elements, neodymium (Nd), and neptunium (Np) concentrations in nuclear
specimens including samples from pyrochemical reprocessing; and 3) the direct elemental and isotopic
analysis of Am in non-separated spent fuel solutions.
REFERENCES
M. Krachler M, R. Alvarez Sarandes, S. Van Winckel, J. Anal. At. Spectrom. 29 (2014) 817-824.
M. Krachler, R. Alvarez Sarandes, P. Carbol, R. Malmbeck, S. Van Winckel, Microchem. J. 110 (2013) 425.
M. Krachler, R. Alvarez Sarandes, S. Van Winckel, J. Anal. At. Spectrom. 28 (2013) 114.
M. Krachler, S. Van Winckel, M. Cardinale, B. Lynch, T. Murakami Microchem. J. 105 (2012) 9.
M. Krachler, P. Carbol (2011) J. Anal. At. Spectrom. 26 (2011) 293.
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4th-INCC 2014 I 4th International Nuclear Chemistry Congress
ASSESSMENT OF METAL ATMOSPHERIC POLLUTION DURING AND AFTER THE
CONSTRUCTION OF A PERIPHERAL HIGHWAY USING TILLANDSIA USNEOIDES
AS BIOMONITOR
Ana Maria Graciano Figueiredo1, Caroline Rodrigues Albuquerque1, Andreza Portella
Ribeiro2, Bárbara Corrigliano da Silva1, Catarina C. Nievola3, Marisa Domingos3, Rubens
C. L. Figueira4
Instituto de Pesquisas Energéticas e Nucleares, IPEN - CNEN/SP, 2Universidade Nove de Julho, 3Instituto de Botânica, IBtSMA/SP, 4Instituto Oceanográfico - IO/USP , São Paulo, Brazil, [email protected]
1
São Paulo city has one of the biggest vehicle fleets in the world, with more than seven million circulating
motor vehicles in the city, which are the main source of atmospheric pollution. The peripheral highway
Mario Covas (SP-21) was planned in order to remove cars and trucks that cross the expanded city center
on their way to other cities. In this study, Tillandsia usneoides (L.) L., an aerial epiphytic bromeliad, was
used as biomonitor aiming to verify if the construction of the western and southern parts of the peripheral
highway SP-21 in São Paulo city would alter the profile of atmospheric contamination by the elements Ba,
Cd, Cr, Cu, Fe, Mo, Ni, Pb, Sb and Zn in the region. These elements are often associated with traffic and
can indicate contaminated urban areas. Neutron Activation Analysis was employed as analytical technique
for the determination of Ba, Cr, Fe, Mo, Sb and Zn. Samples of T. usneoides were irradiated at the IEA-R1
nuclear reactor at IPEN-CNEN/SP, and the induced activity was measured by high resolution gamma-ray
spectrometry. The elements Cd, Cu, Ni and Pb were determined by ICP OES. Increasing concentrations of
the analyzed elements were observed in the biomonitor after the inauguration of the highway, indicating
that these elements originated from vehicular emissions and that the profile of atmospheric contamination
changed in the region.
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
SPATIAL DISTRIBUTION OF NEUTRON FLUX IN GEOLOGICAL LARGE SAMPLE
ANALYSIS AT CDTN/CNEN, BRAZIL
Maria Ângela de Barros Correia Menezes1, Radojko JAĆIMOVIĆ2, Cláubia Pereira Bezerra
Lima3
Nuclear Technology Development Centre, Brazilian Comission for Nuclear Energy, Laboratoy for Neutron Activation Analysis,
CDTN/CNEN, 2Jožef Stefan Institute, Department of Environmental Sciences, 3Federal University of Minas Gerais, School of
Engineering, Department of Nuclear Engineering, Belo Horizonte, Brazil, [email protected]
1
The ideal situation in neutron activation analysis, is one in which the sample and standard are irradiated
in the same neutron flux, i.e. the same number of neutrons, with the same energy distribution. Therefore,
the usual way is to analyse point-source or small samples - up to some milligrams and dimensions of few
millimetres, because several simplifications can be done as to consider negligible the neutron self-shielding,
neutron-flux gradients over the sample and self-absorption of gamma rays.
During the establishing of a methodology to analyse cylindrical soil 5g-sample, considered large sample,
at the Laboratory for Neutron Activation Analysis, CDTN/CNEN, it was necessary to determine the factor
to correct for neutron flux depression due to absorption and scattering during irradiation. The objective
was to verify if spatial inhomogeneity of neutron flux in a large sample would affect the final elemental
concentration results.
Two experiments were performed to determine the neutron flux distribution in geological samples in a defined
volume. One evaluation – axial neutron flux gradient - was based on Fc,Au - factors obtained for Al-0.1% Au
monitors used to elemental concentration calculations, Experiment 1. Other experiment, Experiment 2, was
carried out using iron wires inserted into polyethylene vial.
Basing on Fc,Au – factors, the trend of axial gradient is a linear equation, meaning that for 5g-sample, the
factor value is the correspondent to average height of the sample.
Results based on the specific activities of 59Fe (monitor for thermal neutrons) pointed out that for thermal
neutrons in clay, the radial gradient is about 2%/cm and axial gradient is about 2%/cm.
Based on the specific activities of 54Mn (monitor for fast neutrons), radial gradient for fast neutrons in clay
is about 5%/cm and axial gradient is about 2.5%/cm.
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4th-INCC 2014 I 4th International Nuclear Chemistry Congress
THE WARI INFLUENCE IN THE SOUTH OF PERU: PROVENANACE STUDY OF THE
MIDDLE HORIZON POTERRY FOUND IN THE ARCHEOLOGICAL SITE, LA REAL,
USING k0-INAA
Patricia Socorro Bedregal Salas1, Pablo Antonio Mendoza HIDALGO1, Marco Samule Ubillus
NAMIHAS1, Eduardo Haroldo Montoya ROSSI1
División de Técnicas Analíticas Nucleares, Instituto Peruano de Energía Nuclear, Lima, Peru, [email protected]
1
Hundred of fragments of archaeological pottery, proceeding from a rescue excavation at La Real site, located
in Arequipa, Peru, were studied by instrumental neutron activation analysis, based k0 – method.
Analytical data were processed by multivariate statistical techniques, including a comparison of the chemical
composition of the studied samples, versus the information available in our data bases on the chemical
composition of archaeological pottery from Conchopata (Ayacucho), Cotahuasi (Arequipa), Huaro (Cusco)
and Tiwanaku (Bolivia).
The results obtained revealed that 74 of the studied samples are local from La Real site, while other 21
samples correspond to the chemical composition of other groups, like Conchopata (03), Cusco (09) and
Tiwanaku (04). The remaining 05 samples were not classified, because they presented low probabilities of
belonging to any of the reference groups indicated above, or presented similar probabilities of belonging to
more than one of reference groups.
Some archaeological implications of the obtained results are proposed and discussed.
93
session 9 - Radiation Protection/
Nuclear and Related Techniques
4th-INCC 2014 I 4th International Nuclear Chemistry Congress
The use of Luminescence emission of 3Al2O3-2SiO2: Er phosphors for
environmental dosimetry
Kátia Alessandra Gonçalvez1, Sonia Hatsue Tatumi2
Departamento de Engenharia Elétrica, Universidade de São Paulo, 2Departamento de Ciência do Mar, Universidade Federal de
São Paulo, Santos, Brazil, [email protected]
1
In the present 3Al2O3-2SiO2 were obtained by sol-gel process and morphologically characterized using
Scanning Electron Microscopy (SEM), Transmission Electronic Microscopy (TEM) equipped with Energy
Dispersive Spectrometer (EDS) and X-ray Diffractometry (XRD). According to TEM image it was verified
that the samples present nanocrystal of erbium silicon and erbium oxide on grains boundaries. EDS results
supplied the Er occurrence. XRD powder pattern of the sample 3Al2O3-2SiO2:Er presented phases of mullite,
erbium oxide and erbium silicate.
Optically stimulated luminescence (OSL) properties of powdered 3Al2O3-2SiO2 were analyzed and the
effect of Er incorporation in OSL emission was studied. The samples were produced with concentrations of
2, 4 and 8 mol % of Er, and irradiated with β particles with doses from 1 to 10 Gy. It was verified an increase
in the OSL response, about 30 times when the samples was doped with 8 mol % of Er. Figure 1a) shows OSL
emission of undoped sample irradiated and; Figure 1b) shows OSL response of 8mol% Er doped sample
with the same doses.
TL glow curves of the sample supplied a very large peak, composed by several peaks, as can be observed
from Figure 1c), which displays TL glow curves obtained with 3Al2O3-2SiO2:Er (8 mol %). Er3+ emissions
bands at about 550 and 650 nm, due to the transitions of 2H11/2→ 4I15/2 and 4S3/2→4I15/2 for green emission and
4
F9/2→4I15/2 for red one contributed to TL luminescence. The OSL signal carried out with blue excitation and
detected with optical filter UV-340, therefore the OSL signal is not detected in the visible region as TL glow
curves, there are many Er3+ emission bands in UV region, mainly due to the transitions from 4D7/2, 2H9/2, 2P1/2,
2
P3/2, 4G7/2, 4G11/2 and 4H9/2 to ground state 4I15/2.
Figure 1. OSL decay curves of 3Al2O3-2SiO2 (a) undoped, (b) doped with Er 8 mol% and (c) TL glow
curves supplied by 3Al2O3-2SiO2 (8 mol%).
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
iNDOOR RADON CONCENTRATIONS AT UNIVERSITY CAMPUS AND HOUSES AT
TWO DISTRICTS OF ANKARA,TURKEY
Mehmet Kıldır1, Ali Gökmen2, İnci Gökmen2
Department of Basic Sciences, Faculty of Arts and Sciences, Istanbul Kemerburgaz University, 2Department of Chemistry,
Faculty of Arts and Sciences, Middle East Technical University, İstanbul, Turkey, [email protected]
1
In this study, the indoor radon concentrations in buildings of the Middle East Technical University (METU)
and in houses in Cigdem Mahallesi (CIGDEM) and Dostlar Mahallesi (DOSTLAR) in Ankara were measured
using electrets and results were compared. The statistical analysis of data indicated a lognormal distribution
of radon concentrations. The geometric means (and geometric standard deviations) were 0.65(2.71) for
METU and 2.09(3.37), 2.69(2.54), 2.60(2.74) and 2.09(2.76) for spring, fall and winter1 and winter2 in
CIGDEM, and 0.71(2.83), 1.37(1.68), 2.68(1.71) and 1.73(2.63) for spring, summer, fall and winter in
DOSTLAR, respectively. The lowest radon concentration was observed in METU with reinforced concrete
structures constructed up to goverment standards. In multi-storey modern buildings of CIGDEM with good
building insulation, the radon gas is trapped inside the buildings; yielding higher radon concentrations
without seasonal variation. In DOSTLAR, the observed lower radon concentrations in spring tend to
increase toward winter that may be due to poor insulation in the houses in a slum district.
Keywords: Indoor radon, Electrets, Effective dose, Ankara-Turkey
98
4th-INCC 2014 I 4th International Nuclear Chemistry Congress
A BRIEF RADIATION HISTORY OF THE FUTURE ULTRA COLD NEUTRON
FACILITY AT TRIUMF
Mary Pik Wai CHIN1
TRIUMF, Vancouver, Canada, [email protected]
1
Phased construction of TRIUMF’s Ultra Cold Neutron facility completed successfully in spring 2014. The
first beam is expected by 2016. This work presents a Monte Carlo history, step by step, tracking the first
collision of a 480 MeV proton with a tungsten nucleus in the target, followed by the birth of spallation
neutrons, thereafter successive and varied combinations of projectile-target-ejectile collision. We present a
detail, close-up account of how, as the neutron slowed down, the radiation field developed from the source
proton alone, joined by generations and growing branches of secondary progenies including alphas, He3, tritons, deuterons, muons, pions and neutrinos. Trajectories will be annotated with energy distribution,
conservation and deposition. The work showcases not only the broad range of energy and particle types
FLUKA1 seamlessly simulates, but also its capability in analog transport, allowing extraction of quantities
not measurable by physical detectors.
REFERENCES
1) T. Boehlen, F. Cerutti, M.P.W. Chin, A. Fasso, A. Ferrari, P. Garcia Ortega, A. Mairani, P.R. Sala, G. Smirnov, V. Vlachoudis,
The FLUKA code: developments and challenges for high energy and medical applications, Nuclear Data Sheets, 2014 (in
press).
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
CHEMICAL, RADIOCHEMICAL, SPECTROCHEMICAL AND ISOTOPIC
CHARACTERIZATION OF URANIUM HEXAFLUORIDE USED IN THE
PREPARATION OF NUCLEAR REACTOR FUEL
Olivio Pereira de Oliveira Junior1
Instituto de Pesquisas Enérgeticas e Nucleares (IPEN-CNEN-SP), Sao Paulo, Brazil, [email protected]
1
Uranium hexafluoride plays a central role in the nuclear fuel cycle because it is the most used compound in
the isotope enrichment process. It is stable at room temperature but its high volatility and chemical reactivity
poses a big challenge to processing facilities. Uranium is enriched approximately up to 3.5 to 4.0 % 235U
in mass and then converted to uranium dioxide, form in which it is used in the preparation of the sintered
pellets that eventually feed nuclear reactors. Once enriched, uranium hexafluoride is stored in large cylinders
used for transportation and processing. It is then sampled and transferred to small laboratory cylinders to
allow its characterization, which requires the use of chemical, radiochemical, spectrochemical and mass
spectrometry techniques. This paper describes the technical requirements, analytical instrumentation and
techniques required to fulfill this task.
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session 10 - Radioanalytical Chemistry/
Nuclear and Radiochemistry/
Radioecological and Geochemistry
4th-INCC 2014 I 4th International Nuclear Chemistry Congress
ECOLOGICAL STOICHIOMETRY APPLIED TO SYSTEMATIC BOTANY OF TREE
FAMILIES FROM CERRADO AND ATLANTIC FOREST
Elvis Joacir de FRANÇA1, Elisabete A. De Nadai Fernandes2, Rebeca da Silva Cantinha1
Divisão de Pesquisa e Desenvolvimento, Centro Regional de Ciências Nucleares do Nordeste, Comissão Nacional de Energia
Nuclear, 2Radioisotopes Laboratory, Centro de Energia Nuclear na Agricultura, Universidade de São Paulo, São Paulo, Brazil,
[email protected]
1
Ecological stoichiometry studies the balance of chemical elements in ecosystem compartment interactions.
Brazil is the country of the megabiodiversity concerning to natural resources, flora and fauna. Cerrado
and Atlantic Forest are the hottest hotspot for world conservation. Chemical elements are fundamental
for organisms, thus, understanding their uses are important to study ecological interactions. However,
concerning to tree species, the identification based on chemical element composition at the species level is
not an easy task, since high intra-species and inter-species variability are usually observed. In this work,
chemical element characterization of 23 botanic families from these two biomes was done based on the
chemical fingerprint obtained by instrumental neutron activation analysis – INAA. Tree leaves were
sampled in natural reserves of the state of São Paulo, transported to the laboratory, dried and milled until
particle size of 0.5 mm. The material was irradiated in a thermal neutron flux of 1013 cm-2 s-1at the Research
Nuclear Reactor IEA-R1, Instituto de Pesquisas Energéticas e Nucleares- IPEN, São Paulo, Brazil.k0-INAA
software Quantu was used to calculate the chemical element mass fractions and their expanded analytical
uncertainties at the 95% confidence level. As a result, fingerprints were based on ten chemical elements, in
which Br, Ca, Co, Na and Sc were accumulated in some botanic families, while no significant differences
were observed for Fe, K, Rb, Sr and Zn at the family level. However, these chemical elements could be
helpful for species discrimination by means of cluster analysis. The most accumulator botanic families
were Annonaceae, Apocynaceae, Araliaceae, Clusiaceae, Cyatheaceae, Euphorbiaceae, Nyctagenaceae,
Olacaceae, Penthaphylacaceae, Rubiaceae and Vochysiaceae for both biomes. For Ternstromiaceae family,
no clear fingerprint was identified. Due to the abundance of all tree species analyzed in the ecosystems,
chemical element fingerprint could be useful for ecological restoration based on the knowledge of systematic
botany and ecological stoichiometry.
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
A NEW APPROACH TO Sr-90 MEASUREMENT USING DGA RESIN
Norbert KAVASI1, Sarata K. SAHOO1, Hideki ARAE1, Tetsuo AONO1, Satoshi YOSHIDA1
National Institute of Radiological Sciences, Chiba, Japan, [email protected]
1
The environmental monitoring of Sr-90 is one of the important tasks in Japan after the Fukushima accident.
In this paper we will discuss separation and pre-concentration of Sr-90 from other beta emitter radionuclides
and its application to soil sample analysis.
Sr-90 can be determined shortly after the separation for a short measuring time to avoid the build up its
decay product, Y-90, or after the secular equilibrium (~14 days) between Sr-90 and Y-90.
We have developed a new method to determine Y-90 independently separated from Sr-90 and other interfering
radionuclides after the chemical digestion.
The classical open wet digestion method was applied using a mixture of acids cc. HF, HNO3, and HCl. A
resin called DGA (N,N,N_N_ tetraoctyl-1,5-diglycolamide) was used for separation instead of typically
applied Sr resin. Y shows a higher affinity to the DAG resin in different media (HNO3, HCl) than Sr,
giving rise to the possibility of highly efficient separation. Moreover, there is no uptake of alkaline metals
(except Li), therefore K and Cs isotopes contamination could be avoided. In 5M HCl or 5M HNO3 media,
the retention of Pb isotopes (beta emitters) is negligible thereby eliminating the Pb contamination problem
which occurs through the application of Sr resin.
After the extraction chromatography separation procedure, Y-90 was measured directly using Cherenkov
counter. The detection efficiency was 55% for Y-90, while for Sr-90 it was only 1.6% resulting in negligible
interference originating from Sr-90 contamination. The recovery of the Y was verified using inductively
coupled plasma mass spectrometer.
Since Y is strongly fixed to the DGA resin its efficient elution was difficult, however with 0.01M EDTA
solution the recovery was about ~80%.
REFERENCES
1)A. Pourmand, N.Dauphas, Talanta 81(3) (2010) 741.
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4th-INCC 2014 I 4th International Nuclear Chemistry Congress
PHYSIOLOGICAL AND BEHAVIORAL PARAMETERS AFFECTING THE HAIR
ELEMENT CONTENT OF YOUNG ITALIAN POPULATION
Pasquale Avino1, Geraldo Capannesi2, Luigina Renzi2, Alberto Rosada2
DIPIA, INAIL settore Ricerca, 2UTFISST, ENEA, Rome, Italy, [email protected]
1
The trace elements in hair is a task of considerable interest: they are useful as indicator of body burden
or environmental exposure. In this work we performed hair element characterization of homogeneous
population as well as the relationship between elements and some physiological parameters and environmental
conditions.
The sampling has regarded a population of young people between 14 and 18 years old, 27 males and 104
females, 131 samples. Among the parameters for defining the population critical information was the nosmoker behavior and no-drug consumption.
It has been rated as the content of the inorganic fraction varies according to sex (male, female), the coloring
(blond, brown, reds, blacks), types of hair (wavy, curly, straight), treatment (gel, dye, lacquer, conditioner,
permanent), swimming in the seawater (yes, no) whereas parameters as weight, height and length hair were
considered continuous variables and were not discrete.
Instrumental Neutron Activation Analysis was used for determining about 30 elements. Two irradiations
were carried out at the R.C.-Casaccia’s TRIGA Mark II nuclear reactor. The first irradiation was performed
in the pneumatic channel (Rabbit) for 60 s at a neutron flux of 1.13×1013 n×cm-2×s-1 whereas the second in
the rotating rack (Lazy Susan) for 30 hrs at 2.60×1012 n×cm-2×s-1.
Before performing the INAA determinations, a test was performed to highlight the element release from
scissors. Cr, Fe and Zn were determined in homogeneous hair sample: significant statistical differences were
not found between cut and no-cut hairs. Furthermore, the effect of different sample washings was evaluated
in order to identify the best analytical procedure: the best procedure involves acetone in ultrasonic bath for
10 min at 40 °C.
The chemical analysis and the relative correlation studies between the elements have allowed us to
extrapolate some interesting considerations. The presence of treatments is positively related to the length
of the hair and the female sex. In particular, the permanent treatment is related to sex and length of the
hair but the correlation with lightening and dye treatments is highly significant. The gel is one of the most
popular treatments. The correlations between the parameters and elements show levels of Ba, Zn, I, Ca and
Mg higher in females than in males. The color shows slightly positive correlation values for S, Ba and Mo
whereas the type of hair does not show significant correlations among the various elements. The sea bathing
shows positive correlations with Na, Br, Cl, I and negative with Zn. The treatments showing significant
correlations with the elements are permanent (Ca, Sr, Mg, Ba), dyes (Ca, Sr, Mg, Ba) and lacquer (I, Cr, Au).
Finally, a canonical analysis was performed showing high positive coefficients both for some alkaline-earth
elements (e.g., Ba and Ca) and other of exogenous origin (e.g., Au, Hg, Sc and I).
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
Determination of natural radionuclides 40k, eU and eTh in
environmental samples from the vicinity of Aramar Experimental
Center, Brazil
André Luis Lima de Araújo1, Marco Antônio Proença Vieira de Moraes1, Bruno Burini Robles
Arine1, Rosane Correa Fagundes1, Raquel Medeiros da silva1
Navy Technology Center in Sao Paulo, Sorocaba, Brazil, [email protected]
1
The Aramar Experimental Center is the first uranium enrichment plant in Brazil. The monitoring of natural
background radiation in its surroundings has been held since the year 1988 for different geological and
biological matrices - soil, sediments, fishes, grass and farm products. The natural radioactivity present in all
environments on Earth comes from the radionuclides decay found in rocks and soil, cosmic radiation and its
interaction with atmospheric gases. However, most of the ionizing radiation that affects all organisms arises
from the radionuclides decay of 238U and 232Th series and, secondly, 40K. These, usually occur in low activity,
with no representative risk to the human health. The gamma spectroscopy allows direct determination of
40
K in environmental samples, which respective photopeak is 1460 keV. However, 232Th and 238U are not
gamma radiation emitting radioisotopes and their concentrations are determined indirectly by measuring
the gamma radiation emitted by radiogenic nuclides belonging to the respective decay series. The 238U
and 232Th concentration is estimated by detecting the energy gamma radiation emitted by their daughters
214
Bi and 228Ac, respectively. Due to the indirect estimation, the concentrations of these radioisotopes are
called, respectively, equivalent thorium (eTh) and equivalent uranium (eU). The contents of 40K, eU and eTh
obtained by gamma-ray spectroscopy were converted to annual radiation dose (ARD). The results allowed
evaluating the intensity of natural radiation, whose levels are lower than the international limit of 1000 µSv/
year in the environmental samples from the vicinity of Aramar Experimental Center.
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session 11 - Radiopharmaceutical Chemistry
4th-INCC 2014 I 4th International Nuclear Chemistry Congress
A comparison study of several radioiodinated intermediates for
labelling short peptides
Mohammed Al-Qahtani1, Yousif Al-Malki1
Ciclotron and Radiopharmaceuticals Department, KFSH&RC, Riyadh, Saudi Arabia, [email protected]
1
Objectives: Radioiodinated peptides are one of the important targets for diagnostic and therapeutic
approches in the nuclear medicine field. In this study diferent intermediate radioiodinated labeling agents
were compared on labeling a short peptide.
Methods: All needed reagents and solvents were purchased and used with no further purifications unless
its necessary. Reaction progress was monitored using both Radio-TLC and Radio-HPLC. The eluent was
monitored with a variable-wavelength detector and a flow-through sodium iodide scintillation NaI(Tl)
radioactivity detector. Radioactivity was determined with a dose calibrator. The targeted peptide was
radioiodinated applying diferent intermediate radioiodinated labeling agents.
Figure 1: General Labeleing Scheme.
Results: The targeted peptide was radioiodinated with 123/131I applying diferent intermediate radioiodinated
labeling agents.
Figure 2: (A) Mass-HPLC and (B) Radio-HPLC Chromatograms of Direct Radioiodination prodcut.
Conclusions: The preliminary results indicate that short peptide been labeled in good to excelent
radiochemical yield based on the intermediate radioiodinated labeling agents used.
Research Support: This work was supported by King Abdualaziz City for Science & Technology (AT-2915)
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
POLYMER CONJUGATES OF AUGER ELECTRON EMITTER BEARING
ELLIPTICINES FOR TARGETED CANCER THERAPY
Ondrej Sedlacek1, Jan Kucka2, Jana Mattova2, Martin Parizek3, Martin Studenovsky1,
Marie Zadinova2, Pavla Pouckova2, Martin Hruby1
Institute of Macromolecular Chemistry, Czech Academy of Sciences, v.v.i., 2IInstitute of Biophysics and Informatics, First Faculty
of Medicine, Charles University in Prague, 3Institute of Physiology AS CR, Prague, Czech Republic, [email protected]
1
Auger electrons emitting radioisotopes (such as iodine–125 or indium-111) are a potentially effective cancer
treatment. They are extremely biologically effective, but only within a short range (nanometers). Their use
as an effective cancer therapy requires that they will be transported within close proximity of DNA by an
intercalator, where they induce double-strand breaks leading to cell death. This type of therapy may be even
more beneficial when associated with drug delivery systems1 In this report, we describe an optimized tripletargeted polymer delivery system for the intercalator ellipticine, which contains radioisotope iodine-125
with high specific radioactivity (63.2 GBq/mg). This compound is linked to an N-(2-hydroxypropyl)
methacrylamide copolymer via an optimized acid-sensitive hydrazone linker. The system is stable at pH
7.4 (representing the pH of blood plasma), and the radioiodine-containing biologically active intercalator
is released upon a decrease in pH (44% of the intercalator is released after 24 h of incubation in pH 5.0
buffer, which mimics the pH in late endosomes)2 The active compound is a potent intercalator, as shown
with direct titration with a DNA solution, and readily penetrates into cell nuclei, as observed by confocal
microscopy. Its polymer conjugate is internalized into endosomes and releases the radioactive intercalator,
which accumulates in the cell nuclei. In vivo experiments on mice with 4T1 murine breast cancer resulted in
a statistically significant increase in the survival of mice treated with the polymer radioconjugate. The free
radiolabeled intercalator was also shown to be effective, but it was less potent than the polymer conjugate.
Financial support provided by the Ministry of Industry and Trade of the Czech Republic (grant # MPO TIP
FR-TI4/625) is gratefully acknowledged.
REFERENCES
1)O. Sedlacek, M. Hruby, M. Studenovsky, J. Kucka, D. Vetvicka, L. Kovar, B. Rihova and K. Ulbrich, Bioconjugate
chemistry 22 (2011), 1194-1201.
2)O. Sedlacek, M. Studenovsky, D. Vetvicka, K. Ulbrich, and M. Hrubý, Bioorganic & medicinal chemistry 21(2013), 56695672.
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4th-INCC 2014 I 4th International Nuclear Chemistry Congress
RADIOLABELED NANOPARTICLES AND RECENT APPROACHES
Serap Teksöz1, Çiğdem İçhedef1, Eser Uçar1, Kadir Arı1
Ege University, Institute of Nuclear Sciences, Department of Nuclear Applications, Izmir, Turkey, [email protected]
1
Radiolabeled nanoparticles represent a novel class of radiopharmaceutical agents with great potential in
diagnosis and personalized treatment of various diseases such as cancer in particular. Among these, the
development of novel targeting drug systems has been an active field of study for at least two decades.
Nano-sized drug delivery systems are promising as developed solutions to make drugs tumor-specific and
to avoid their side effects. Recently, solid lipid nanoparticles (SLN) containing anti-cancer agents have
received the advantage of anti-cancer drug delivery systems. In addition to the drug delivery systems,
radionuclide-based tumor therapy and diagnostic methods are widely used techniques. Pharmaceuticals or
molecules labeled with radionuclide can be transported into the tumor, which is the function of treatment or
diagnosis the tumor cells. Various radioactive nanoparticles have the advantage of being able to deliver high
concentrations of radioactivity to the target area, without damaging normal surrounding tissue as well. It’s
predicted that these new complexes will find a wide spread field in creation of materials besides medicine
in near future.
REFERENCES
1. Chen L.C., Chang C.H., Yu C.Y., Chang Y.J., Hsu W.C., Ho C.L., Yeh C.H., Luo T.Y., Lee T.W., Ting G., Nucl. Med. Biol. 34
(2007) 415–423.
2. Hong H., Zhang Y., Engle J.W., Nayak T.R., Theuer C.P., Nickles R.J., Barnhart T.E., Cai W., Biomaterials 33 (2012) 41474156.
3. Bagul R., Mahajan V., Dhake A., Int. Curr. Pharm. J. 4 (2012) 29-38.
4. Andreozzi E., Seo J.W., Ferrara K., Louie A., Bioconjugate Chem. 22 (2011) 808–818.
5. Psimadas D., Bouziotis P., Georgoulias P., Valotassiou V., Tsotakos T., Loudos G., Contrast Media Mol. Imaging. 8 (2013)
333–339
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
A PERSPECTIVE ON PLANT ORIGIN RADIOLABELED COMPOUNDS, THEIR
BIOLOGICAL AFFINITIES AND INTERACTION BETWEEN PLANT EXTRACTS
WITH RADIOPHARMACEUTICALS
Zumrut Fazilet Biber Muftuler1, Ayfer Yurt Kilcar1, Perihan Unak1
Institute of Nuclear Science, Ege University, 2Izmir, Turkey, [email protected]
1
Nowadays; medicinal plants, such as fruits and vegetables, are consumed very much and intensity of the
traditional use of them are becoming increasingly important. Medicinal plants have protective effect on
human health due to their high and natural antioxidant capacity. In epidemiologic studies it is observed that
there is an interaction between vegetable consumption and cancer prevention. A large body of epidemiological
evidence, together with data from in vivo and in vitro studies, has brought the proof of plant’s cancerpreventive properties. Depending on this knowledge nowadays there is a swift increase in consumption
of these medicinal plants. Plants, an easily available natural material of low cost, share possibly a similar
wealth of health benefiting bioactive phytochemicals.
Cancer is still the second leading cause of death all over the world. Therefore, natural plant origin
products which have anticancer and antitumor properties are come into prominence. In recent years, there
is a significant increase on the production of compounds from natural plants and purification of them to
investigate the potential use at the treatment and diagnosis of diseases, cancer in particular. Recently, more
scientific interest has been focused on plant origin radiolabeled compounds.
Furthermore, in recent years all over the world, medicinal plants are consumed quite a lot; however, side
effects of biological and chemical contents and radiopharmaceutical interactions for each consumer in
question aren’t entirely well-known. Due to this uncontrolled consumption of people without the knowledge,
researches focused on investigation of interactions between radiopharmaceuticals and plant extracts. The
studies of plant origin extract or drug interaction with radiopharmaceuticals are highly relevant and desired.
Consequences of these investigations may cause to reduce the risk of misdiagnosis and/or avoid the repetition
of the examinations in Nuclear Medicine.
Current review carried out to evaluate the contribution of plant product extract for the development of new
plant origin radiolabeled agents for imaging or therapy and to investigate the interactions of plant extracts
with radiopharmaceuticals. There are studies in this content which are investigated utilizing various in
vitro (cell lines, cancer cell lines, bacteria, wound healing) methods and in vivo (radiolabeling of blood
cells, biodistribution) methods. Consequently, we summarize the current understanding, together with other
known examples of plant origin radiolabeled agents, interaction between plants and radiopharmaceuticals.
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session 12 - Radiation Chemistry/
Radioecological and Geochemistry
4th-INCC 2014 I 4th International Nuclear Chemistry Congress
SYNTHESIS OF PAPAIN NANOPARTICLES USING E-BEAM AND GAMMA
IRRADIATION: A RADIATION CHEMISTRY APPROACH
Gustavo Henrique Costa Varca1, Sławomir Kadłubowski2, Marian Wolszczak3, Ademar
Benévolo Lugão4, Janusz M. Rosiak5, Piotr Ulanski6
Instituto de Pesquisas Energéticas e Nucleares, 2Institute of Applied Radiation Chemistry, 3Lodz University of Technology,
IPEN, 5Lodz University of Technology, 6IPEN, São Paulo, Brazil, [email protected]
1
4
The use of irradiation for the development of advanced materials and devices at nano or micro scale has
been detailed over the years. Advantages of this technique include the possibility to apply the irradiation
inside the final package, no considerable temperature increase, and the possibility to combine simultaneous
features along the process, depending upon the irradiation source. In this work we report the use of
irradiation, gamma and e-beam sources, for the development of nanostructured protein based drug carriers,
as an alternative technique for controlled protein crosslinking. In a more specific way, the aim is to develop
papain nanoparticles by the use of distinct radiation sources on a radiation chemistry point of view. On this
account Papain was solubilized in phosphate buffer and submitted to irradiation at 10 kGy as a function
of ethanol concentration. Optimized concentrations were selected for evaluation of the dose effect, with
irradiation doses ranging from 2.5-10kGy. Particle size changes were monitored by DLS. Fluorescence
measurements were applied in order to verify bityrosine formation. Nanoparticles were achieved in the
range of 5 to 11nm approximately, depending upon ethanol concentration and irradiation dose. Fluorescence
experiments revealed an increase in bityrosine formation highlighting the nanoparticle formation in both
cases. Thus both irradiation sources was suitable for the synthesis of papain nanoparticles to be applied for
biotechnological purposes.
REFERENCES
1) K. Furusawa, K. Terao, N. Nagasawa, F. Yoshii, K. Kubota, T. Dobashi, Colloid. Polym. Sci. 2004, 283, 229-233.
2) G. H. C. Varca, C.C. Ferraz, P. S. Lopes, M. B. Mathor, M. Grasselli, A. B. Lugao, Rad. Phys. Chem. 94 (2014) 181-185.
3) G.H.C. Varca, G.G. Perossi,, M. Grasselli, A.B., Lugao, Radiat. Phys. Chem. 2014. DOI: 10.1016/j.
radphyschem.2014.05.020
4) S.L. Soto Espinoza, M.L. Sánches, V. Risso, E.E. Smolko, M. Grasselli, Radiat. Phys. Chem. 2012, 81, 1417-1421.
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
Model of diffusion-convection of 137Cs for the determination of
recent sedimentation rates
Paulo Alves de Lima Ferreira1, Rubens Cesar Lopes Figueira2
Instituto Oceanográfico, Universidade de São Paulo (IO-USP), 2Instituto Oceanográfico, Universidade de São Paulo (IO-USP) ,
São Paulo, Brazil, [email protected]
1
Radioanalytical methods stand out in the Earth Sciences due to several advantages, such as no destruction of
samples, no need for chemical treatments and ease of data determination from nuclides of easy identification
and separation from their non-radioactive isotopes. This study validated the model of diffusion-convection
(MDC) of 137Cs for the calculation of recent sedimentation rates from 13 sedimentary columns of two
Brazilian coastal systems: the Estuarine System of Cananeia-Iguape and Estuarine System of Santos-São
Vicente. 137Cs, one of several isotopes of Cs, is a radionuclide artificially produced by fission of 235U, and
presents environmental characteristics such as a high fission yield and half-life of 30.17 years, and its model
covers key factors responsible for its vertical migration: its diffusion to the interstitial water and the vertical
convection of this water through the sediments1. The mean sedimentation rates determined were 1.03 ±
0.17 cm y-1 for Cananeia-Iguape, 1.05 ± 0.39 cm y-1 for the Bertioga Channel and 0.91 ± 0.10 cm y-1 for the
Upper Santos Estuary, validated with unsupported 210Pb models. From the results of the MDC of 137Cs for
the studied coastal systems, it was possible to obtain oceanographic interpretations of sedimentation based
only on data from sedimentation rates, corroborated by information previously determined by other studies
in such areas2,3,4.
REFERENCES
1) P. A. L. Ferreira, A. P .Ribeiro, M. G. Nascimento, C. C. Martins, M. M. Mahiques, R. C. Montone, R. C. L. Figueira, Sci.
Tot. Environ. 443 (2013) 505.
2) C. Gonçalves, R. C. L. Figueira, J. R. Sartoretto, A. B. Salaroli, A. P. Ribeiro, P. A. L. Ferreira, M. M. Mahiques, Braz. J.
Oceanogr. 61 (2013) 149.
3) M. M. Mahiques, R. C. L. Figueira, A. B. Salaroli, D. P. V. Alves, C. Gonçalves, Environ. Earth Sci. 68 (2013) 1073.
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4th-INCC 2014 I 4th International Nuclear Chemistry Congress
DECOMPOSITION OF URANYL PEROXO-CARBONATO COMPLEX IONS IN THE
PRESENCE OF METAL OXIDES IN CARBONATE MEDIA
Dong-Yong CHUNG1, Min-Sung PARK1, Keun-Young LEE1, Eil-Hee LEE1, Kwang-Wook KIM1, JeiKwon MOON1
Korea Atomic Energy Research Institute, Daejeon, South Corea, [email protected]
1
A feasibility and basic study to find a possibility to develop such a process for recovering U alone from
spent fuel by using the methods of an oxidative leaching and a precipitation of U in high alkaline carbonate
media was newly suggested with the characteristics of a highly enhanced proliferation-resistance and more
environmental friendliness1 In carbonate solutions with hydrogen peroxide, uranium oxides were dissolved
in the form of uranyl peroxo-carbonato complexes, UO2(O2)x(CO3)y2-2x-2y, (x/y=1/2 and 2/1)2 H2O2 is known
to be decomposed into water and oxygen in alkaline solutions. Accordingly, evaluation of the stability of
uranyl peroxo-carbonato complexes of UO2(O2)x(CO3)y2-2x-2y is very necessary to ensure the concentration
does not change during prolonged storage in the carbonate-based process3 When UO2(O2)x(CO3)y2-2x-2y lose
their peroxide component, they change into stable species of UO2(CO3)34-. However, there have been very
little studies on the stability of such uranyl peroxo-carbonato complex ions in the presence of the various
oxides in carbonate solution. In this study, decomposition of the uranyl peroxo-carbonato complexs in
carbonate solution was investigated at in the presence of several metal oxides using absorption spectroscopy.
REFERENCES
1) K. W. Kim, D. Y. Chung, H. B. Yang, J. K. Lim, E. H. Lee, K. C. Song, K. S. Song, Nucl. Technol. 166 (2009) 170.
2) D. Y. Chung, H. S. Seo, J. W. Lee, H. B. Yang, E. H. Lee, K. W. Kim, J. Radioanal. Nucl. Chem. 284 (2010) 123.
3) K. W. Kim, K. Y. Lee, D. Y. Chung, E. H. Lee, J. K. Moon, D. W. Shin, J. Hazardous Materials 233-234 (2012) 213.
117
poster session
1
Education in Nuclear Chemistry
4th-INCC 2014 I 4th International Nuclear Chemistry Congress
NEUTRON ACTIVATION ANALYSIS AND ITS APPLICATION TO DETERMINE THE
CONCENTRATION OF ELEMENTS IN COMPLEX MATRICES
Valerian LOBO1
Wollo University, Dessie, Etiópia, [email protected]
1
Activation analysis is the identification and quantification of unknown elements from their characteristic
emissions and decay constants after they have been made radioactive by exposure to neutron or charged
particle radiation. Activation analysis is one of a number of techniques used to accurately determine the
concentrations of elements in a sample. Neutrons being neutral in charge are being less hindered by the
target nuclei than the charged particles. Therefore neutron activation analysis is more commonly used.
Neutron activation analysis was discovered in 1936 by Hevesy and Levi. They found that samples containing
some rare earth elements became radioactive after exposure to a source of neutrons. With respect to time
of measurements, neutron activation analysis falls into two categories: 1) Prompt gamma-ray neutron
activation analysis, where measurements take place during irradiation. 2) Delayed gamma-ray neutron
activation analysis where measurements follow radioactive decay. Delayed gamma-ray neutron activation
analysis is flexible with respect to time. In this method sensitivity for a long lived isotope that suffers from
an interference by a short-lived radionuclide can be improved by waiting for the short-lived radionuclide
to decay. This selectivity is a key advantage of delayed gamma-ray neutron activation analysis over other
analytical methods. The gamma-ray measurement in the activated samples is done with instrumentation
having semiconductor detectors, associated electronics and a computer based multichannel analyzer.
Hyper-pure Germanium (HPGe) detectors consisting of germanium crystal in a vacuum cryostat thermally
connected to copper rod which operate at liquid nitrogen temperature (-77 K) are generally used.
This process produces radioactive isotopes by irradiating samples to high flux of neutrons from isotopic
neutron source (252Cf) or nuclear reactors. The isotopes typically decay by beta-decay and in the process
gamma-rays with discrete energies are emitted. These discrete energies are the finger prints for an isotope.
An advantage of gamma rays is that many are much more energetic than X-rays; therefore gamma rays
are less readily absorbed and matrix corrections are not usually important. By irradiating standards along
with the samples and using comparator method, the abundances and concentration of elements in various
samples such as soil samples, etc., have been determined.
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
Knowledge about nuclear energy and radioactivity of senior
high school students
Aline Sabastiane Gonçales Ramos de Oliveira1, Lucio Leonardo1-2, Sandra Regina Damatto1
Laboratório de Radiometria Ambiental - Instituto de Pesquisas Energéticas e Nucleares (IPEN / CNEN), 2 Universidade Paulista
- UNIP, São Paulo, Brazil, [email protected]
1
Contrary to what many Brazilians think, Brazil is considered a country of nuclear activities. The country
began to develop an interest in the area in the 1930s with the beginning of the early researches and after the
nuclear bombs of Hiroshima and Nagasaki the Brazilian military verified the importance of the knowledge
and domain of nuclear energy for military strategic purposes. In 1969, Brazil developed its first nuclear
program and initiated the establishment of the first nuclear power plant. Currently, there are two plants
in operation in Brazil and a third one is being implemented; they’re all located in the city of Angra dos
Reis, state of Rio de Janeiro. There are also other related nuclear activities in the country, such as the
exploitation of radioactive minerals, research and production of radiopharmaceuticals and technologies to
generate products and nuclear services. The Brazilian government, worried about educational questions,
established some pedagogical guidelines to ensure that all students leave high school with sufficient
knowledge to evaluate new technologies critically. The document in which these guidelines are found is
called Supplemental Educational Guidelines for National Curriculum Parameters of Secondary Education
(PCNEM), and issues about radioactivity and nuclear energy can be found in it. The document also states
that the students must know the nuclear properties, production and use of nuclear power, the risks and
benefits, and major social uses of this form of energy. After the initiative of the Brazilian government of
including themes related to nuclear energy and radioactivity in the high-school curriculum, questioning
of what would be the perceptions and the level of knowledge about these themes by senior high-school
students emerged. To evaluate whether students are getting the knowledge given in PCNEM, a questionnaire
consisting of multiple-choice questions and open questions on the topics has been elaborated. The sample
selected for the survey was graduating high school students from public and private institutions in the city
of São Paulo. National literature shows in several studies that levels of understanding of the issues by the
students are below those indicated by the Ministry of Education, which confirms the results of this research.
In the present work it was found that students know very little about nuclear energy and radioactivity, believe
many myths about nuclear energy and are not able to analyze critically the advantages and disadvantages of
this form of energy.
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Nuclear and Radiochemistry
4th-INCC 2014 I 4th International Nuclear Chemistry Congress
MECHANISM OF UO2(NO3)2×6H2O DECOMPOSITION UNDER MICROWAVE
IRRADIATION
Sergey A. KULYUKHIN1
Institute of Physical Chemistry and Electrochemistry, Russian Academy of Science, Moscow, Russia, [email protected]
1
Spent nuclear fuel (SNF) reprocessing results in accumulation of low- (LLW) and intermediatelevel (ILW)
liquid wastes containing uranium and other fission products. Along with radionuclides, LLW and ILW
contain large amount of salts, including alkali and alkaline-earth metal nitrates. Prior to disposal, liquid
LLW and ILW are usually concentrated by evaporation, in particular, in various difficultly soluble matrices.
For example, superstoichiometric sorption of Cs, Sr, and actinides on silica gel from liquid radioactive waste
(LRW) allows preparation of the final product, silica gel matrix containing 500, 200, and 700–1400 mg g–1
of these elements, respectively.
One of the ways to prepare ILW and LLW for disposal is their direct evaporation in special metallic
containers used for radioactive waste (RW) storage. Recently it was suggested to use for this purpose
microwave radiation (MWR). The disposal of uranium RW and the U regeneration are urgent problems. Use
of MWR for this purpose seems to be very important, taking into account such advantages of this process as
considerable acceleration of the dehydration and formation of products meeting the norms for RW disposal
and storage. Our goal was to study decomposition of uranyl nitrate in a silica gel matrix under MWR
treatment, identification of the products formed, and comparison with the mechanism of decomposition
of crystalline UO2(NO3)2·6H2O and of uranyl nitrate immobilized in a silica gel matrix in the form of an
aqueous solution.
The influence of microwave irradiation (MWI) on the decomposition of UO2(NO3)2·6H2O was studied. The
UO2(NO3)2·6H2O decomposition products arising under MWI were investigated using thermogravimetric
and X-ray phase studies, as well as IR spectroscopy and electron microscopy.
The results of the physicochemical studies of the decomposition products were compared with the literature
data for different uranium compounds, including UO2(NO3)2·6H2O.
The physicochemical studies of the decomposition products and the measurements of [UO22+] and [NO3-]
and of the molar ratio between NО3- and UO22+ in different fractions of the decomposition product show that
in addition to gaseous products, the end decomposition products of 2-10 g of UO2(NO3)2·6H2O under MWI
during 35 minutes (a maximum temperature of the process 170-320оС is achieved in the first 2-5 minutes
of the irradiation) are the UO2(OH)NO3 uranylhydroxinitrate and UO3 uranium trioxide or their hydrates.
The solubility of UO2(OH)NO3 in H2O at 20оС was measured. It was equal to 6.83·10-2 mol/l. The obtained
results are consistent with the UO2(NO3)2·6H2O decomposition under MWI which can be described by the
following reactions:
(1) UO2(NO3)2·6H2O àUO2(OH)NO3 + 5H2O + HNO3 and (2) UO2(OH)NO3 à UO3 + HNO3.
The mechanism of the UO2(NO3)2·6H2O decomposition under MWI differs from its thermal decomposition
mechanism during convection heating in that the major precursor for UO3 as a UO2(NO3)2·6H2O
decomposition product is only UO2(OH)NO3 or its hydrates. No formation of UO2(NO3)2 or its hydrates is
observed.
A study of the MWI effect on the decomposition of UO2(NO3)2·6H2O placed in a silica gel matrix showed
that after MWI of the silica gel - UO2(NO3)2·6H2O system during 35 minutes, the water leaching of uranium
from silica gel during 24 hours was not higher than 10-15% of the total uranium content in the silica gel
matrix.
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SORPTION OF UO22+ ON SORBENTS BASED ON MODIFIED SILICA GEL
CONTAINING Cu, Ni, AND Zn FROM AQUEOUS SOLUTIONS
Sergey A. KULYUKHIN1, Margarita P. GORBACHEVA1
Frumkin Institute of Physical Chemistry and Electrochemistry, Russian Academy of Science, Moscow, Russia, [email protected]
1
Uranium radionuclides are one of the biologically hazardous nuclear fuel elements penetrating into the
environment as a result of human activity in nuclear engineering. Uranium may be present in the environment
in different oxidation states. However, the most widely spread is mobile form is UO22+.
In addition, the presence of CO32- ions in aqueous solutions leads to the formation of neutral and negative
complexes with UO22+, which have a high migration ability. To decrease the uranium migration, it has
been proposed to carry out the reduction of UO22+ to U4+ with the help of materials containing Fe or Fe-Ni
nanoparticles.1 The UO22+ reduction results in the formation of UO2. It was found that adding Ni to Fe
leads to not only the stabilization of F nanoparticles, but also an increase in the UO22+ reduction degree.
The aim of this work was to study the interaction of UO22+ in aqueous solutions of varied
compositions with modified sorbents based on large-pore silica gels containing Cu, Ni, and Zn.
A study of the interaction of aqueous solutions of UO22+ with the modified sorbents based on the largepore silica gel containing Cu, Ni, and Zn was carried out. It was shown that the sorption of UO22+
occurred on all sorbents. The decontamination factors for 10-2 M aqueous solutions of UO22+ on pure largepore silica gel, as well as on the sorbents containing Cu, Ni, and Zn are of the same order of magnitude
and were not higher than 100. For 1.1⋅10-1 M aqueous solutions of UO22+, the decontamination factors on
the pure large-pore silica gel and modified sorbents containing Cu, Ni, and Zn were also of the same order
of magnitude, but their values were not higher than 10.
The interaction of the modified Ni-containing sorbent with the UO22+ solution yielded a dark-green residue
of the composition NiU(OH)6⋅4N2H5OH; i.e., the reduction of UO22+ to U4+ took place.
REFERENCES
1). O. Riba, Th. B. Scott, G. C. Allen, Abstracts of 11th Inter. Conf. on Chemistry and Migration Behaviour of Actinides and
Fission Products in the Geosphere “Migration’07”, Munich, Germany (2007) 201.
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4th-INCC 2014 I 4th International Nuclear Chemistry Congress
FORMATION OF NITROGEN OXIDES DURING URANIUM NITRIDE DISSOLUTION
IN NITRIC ACID
Alexei A. Bessonov1, Sergey A. KULYUKHIN2, Andrey Yu. Shadrin3, Yulia A.
Voskresenskaya4, Oleg A. Ustinov5
Frumkin Institute of Physical Chemistry and Electrochemistry, Russian Academy of Science, 2Open joint-stock company
VNIINM, Moscow, Russia, [email protected]
1
According to paper1, the dissolution of UN in HNO3 occurs to form different gaseous nitrogen derivates
(N2O, NO, NO2, and N2). The composition of the gas phase varies depending on the HNO3 concentration.
The authors showed that the during UN dissolution in HNO3 with a concentration of up to 6 mol/l, the
volume content of N2O and NO in the gas phase was 1-30 and 15-40 vol.%, respectively, whereas almost
no formation of NO2 was observed. Increasing the HNO3 concentration in the gas phase led to an abrupt
decrease in the N2O volume concentration, whereas the amount of NO2 increased.
The absence of NO2 in the gas phase during UN dissolution in HNO3 found in1 is quite an interesting
fact. The aim of this work was a study of the formation nitrogen oxides in the gas phase during UN
dissolution in HNO3 as a function of both the HNO3 concentration and UN amount.
We studied the dissolution of 210-220 mg of UN in 1.5 ml of 3-16 mol/l HNO3 and 50-500 mg of UN in
1.5 ml of 7.2 mol/l HNO3 at 50-60оС in the argon and air. To study the formation of nitrogen oxides,
we used a specially designed laboratory facility which allows to carry out experiments on UN dissolution
in HNO3 under different experimental conditions. The composition of the mixture of nitrogen compounds,
except N2, in the gas phase was studied using IR spectrometry. The measurements of the IR spectra were
fulfilled in gas cells (working space length 10 cm) using a Specord M80 spectrometer. Before the IR spectra
measurements, the pressure in the gas cells was brought to the atmospheric value by addition of gaseous
nitrogen. The quantitative evaluation of the concentrations of nitrogen oxides was carried out according the
band ν = 2236cm-1 for N2O, ν = 1792cm-1, for NO, and ν = 1628cm-1 for NO2.2 The measurement accuracy
was ±10%. The study of the IR spectra of the gas phase formed during the dissolution of 217 mg of UN
in 1.5 ml of 3-16 mol/l HNO3, in contrast to the data reported in1, always showed the formation N2O, NO,
and NO2. In addition, the dissolution of UN in HNO3 with a concentration higher than 9 mol/l led to the
accumulation of N2O4. We found that decreasing the HNO3 concentration from 16 to 3 mol/l increased
the time of a complete dissolution of 217 mg of UN from 1 to 20 min.
The study of the IR spectra allowed us to calculate the amounts of N2O, NO, and NO2 in the gas phase
formed during the dissolution of UN in 3-16 mol/l HNO3 in the Ar and air, respectively (Figs. 1 and 2). The
amount of N2O in the gas phase formed during the dissolution of UN increases linearly in either the
Ar atmosphere or air atmosphere (Figs.1,2). On the other hand, the dependencies for NO and NO2 are of
a more complex character, which might be due to the possible transformation of NO into NO2 and NO2 into
N2O4.
Figs. 3 and 4 show the data on the accumulation of different nitrogen oxides in the gas phase during the
dissolution of 50-500 mg of UN in 1.5 ml of 7.2 mol/l HNO3 in the Ar and air, respectively. The study of the
IR spectra of the gas phase showed the formation of N2O, NO, and NO2 in all these cases. We found that
increasing the amount of UN increased the time of its dissolution from 2-3 to
∼5-6 min. It should be noted finally that the accumulation of the nitrogen oxides in the gas phase during UN
dissolution in HNO3 is a complex process depending on many factors, with the curves of the accumulation
of the nitrogen oxides not being linear functions.
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
REFERENCES
1) L. M. Ferris, J. Inorg. Nucl. Chem. 30 (1968) 2661.
2) IR database. IR-Spektrensammlung der ANSYCO GmbH // http://www.ansyco.de/CMS/frontend/index.php/idcatside=124&s
id=6709b6849ec5584edccda367912d2393. Site visit date: 22.10.2013
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ABSORPTION OF NITROUS OXIDE IN AQUEOUS SOLUTIONS OF GAS CLEANING
SYSTEM IN TECHNOLOGICAL SCHEMES OF UN DISSOLUTION
Sergey A. KULYUKHIN1, Andrey Yu. Shadrin2, Alexei A. Bessonov1, Yulia A.
Voskresenskaya2, Oleg A. Ustinov2
Frumkin Institute of Physical Chemistry and Electrochemistry, Russian Academy of Science, 2Open joint-stock company
VNIINM, Moscow, Russia, [email protected]
1
The gaseous wastes of spent nuclear fuel reprocessing plants may include different volatile radioactive
components, which depends on the fuel reprocessing flowchart, the fuel composition, the fuel burnout extent,
the fuel cooling time, and other factors. The composition of the gaseous wastes in each reprocessing stage
varies too. Thus, the fuel dissolution stage is associated with the fuel destruction, which results in the release
of all fission products, with gaseous fission products going into the gas phase, which before its discharge
into the environment is subjected to decontamination at special setups. As a rule, the gas decontamination
systems includes a lot of various units (filters, absorbers, scrubbers with different solutions, condensers,
drop catchers, etc.) to absorb radioactive aerosols, gaseous and vaporous fission products, as well as various
gases emerging during spent nuclear fuel destruction.
During the dissolution of nitride fuel in HNO3, not only fission products, but also nitrogen oxides (N2O,
NO, and NO2) go into the gas phase, and these oxides are to be removed from the gas phase too. Virtually
a quantitative isolation of NO and NO2 from the gas flow can be provided using various liquid traps. On
the other hand, N2O is known as a not salt-forming oxide that can hardly react with either alkalis or acids.
However, a complete or partial absorption of N2O is possible, when the gas flow is passed through different
aqueous solutions. Since literature data on the absorption from the gas flow under dynamic conditions is
unavailable, the solution of this problem has become the aim of this work.
We studied the absorption of N 2Ofrom an air flow in water, 7.2 and 16 mol/l HNO 3, 1.0 n NaOH,
0.5 mol/l (NH 2) 2CO, 1.0 mol/l N 2H 4⋅nH 2O, 0.1 n KMnO4, 0.1 nK2Cr2O7, concentrated NH4OH, a
mixture of 0.1 n KMnO4 with concentrated HNO3 (or concentrated H2SO4) at a molar ratio of 2 : 1, as
well as in а saturated solution of K2Cr2O7 in concentrated H2SO4 at 20-25оC. In addition, because N2O
absorption may occur during the dissolution of UN in HNO3, we also studied N2O absorption in 0.2 mol/l
by in an nitro-acid solution of UO2(NO3)2 with pH ∼2. To study N2O absorption from the gas flow, we
used a specially designed laboratory stand with bubblers of different designs. The gas flow rate through
the aqueous solutions was 0.12-0.22 l/min. The N2O absorption rate in the solutions was calculated from
the initial and final amounts of N2O measured using IR-spectroscopy. The measurements of the IR spectra
were carried out in gas cells (working space length 10 cm) using a Specord M80 spectrometer. Before the
IR measurements, the pressure in the gas cells had been brought to the atmospheric value using gaseous
nitrogen. The quantitative evaluation of the N2O content was carried out according to the band ν = 2236 cm-1
(ε = 0.2244 mol-1⋅cm-1).1 The measurement accuracy was ±10%.
The Table shows the data on the N2O absorption in different aqueous solutions. As seen in the Table, the
N2O absorption peaks under the studied experimental conditions were reached for the saturated solution
of K2Cr2O7 in concentrated H2SO4 (∼30%) and water (∼22.6%). For concentrated HNO3 and NH4OH, as
well as 1.0 mol/l NaOH and N2H5OH, the N2O absorption degree was within a range of (∼7.5 - ∼11.5)%.
A close absorption degree was also reached in 0.5 mol/l (NH2)2CO (∼11%). In the other solutions, the N2O
absorption rate was not higher than ∼4.0%.
We also studied the influence of the size of the bubbler nozzles and the amount of the solutions on the N2O
absorption was also studied.
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
REFERENCES
1). IR database. IR-Spektrensammlung der ANSYCO GmbH // http:// www.ansyco. de/CMS/ frontend/ index.php/idcatside =
124&sid=6709b6849ec5584edccda367912d2393. Site visit date: 22.10.2013
Table. Data on the N2O absorption in different aqueous solutions at 20-25оС
(V = 30 ml, h = 60 mm, d = 28 mm, ∅ = 1 mm, υ = 0.12-0.22 l/min)
#
1
2
3
4
5
6
7
8
9
10
11
12
13
14
Aqueous solution
N2O amount, mM
initial
final
H2O
HNO3 (conc.)
HNO3 (conc.)
7.2 M HNO3
NH4OH (conc.)
1.0 N NaOH
1.0 M N2H5OH
0.5 M (NH2)2CO
0.1 N KMnO4
0.1 N KMnO4 + H2SO4 (conc.)
0.1 N KMnO4 + HNO3 (conc.)
0.2 M UO2(NO3)2
0.1 N K2Cr2O7
satur. K2Cr2O7 in H2SO4 (conc.)
1.52
1.52
1.79
1.47
1.61
1.61
1.88
1.70
1.61
2.05
1.88
1.56
1.79
2.05
1.17
1.41
1.65
1.46
1.46
1.43
1.67
1.51
1.54
2.05
1.80
1.55
1.74
1.43
N2O
absorption
rate, %
22.6
7.4
7.8
0.9
8.9
11.1
11.2
11.1
3.9
0
3.8
0.3
2.8
30.2
Note: V is the volume of the aqueous solution, h is the height of the absorbing layer of the solution, d is the
bubbler diameter, ∅ is the diameter of the bubbler nozzle, and υ is the bubbling rate.
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4th-INCC 2014 I 4th International Nuclear Chemistry Congress
Np(V)-PHENANTHROLINE-DiCARBOXYLIC ACID COMPOUNDS:
SYNTHESIS, STRUCTURE, PROPERTIES
Alexei A. Bessonov1, A.B. Yusov1, I. A. Charushnikova1, A. M. Fedosseev1
Frumkin Institute of Physical Chemistry and Electrochemistry, Russian Academy of Sciences, Moscow, Russia, [email protected]
1
Complexes of Np(V) with 1,10-phenanthroline-2,9-dicarboxylic acid, C12H6N2(COOH)2 (H2PDA),
(I),
(NH4)2[NpO2(PDA)]2·3H2O
(II),
and
of
compositions
[(NpO2)2(PDA)(H2O)3]·H2O
[C(NH2)3]2[NpO2·(PDA)]2·4H2O (III) were synthesized. The Np atoms in the crystal lattices of all the
compounds have the pentagonal bipyramidal coordination surrounding, with the [C12H6N2(COO)2]2– anions
acting as chelate-bridging N,O-donor ligands. In the structure of I, two crystallographically independent
NpO2+ dioxocations participate in the cation–cation
interaction leading to the formation of tetrameric cation–cation complexes. The nonequivalence of the Np
atoms is manifested in splitting of the main absorption band of Np(V) in the electronic spectrum of solid
compound I. The structures of II and III are based on dimeric anionic complexes [NpO2(C12H6N2(COO)2)]2 2–.
Only one kind of complexes, NpO2(PDA)–, was detected in the solution. The high value of the concentration
stability constant β~1012L.mol–1 was found due to tetradentate coordination of the ligand.
133
4th International Nuclear Chemistry Congress I 4th-INCC 2014
Uranyl Nitrate Hydrolytic Behavior in the Presence of Reductant
Alexei A. Bessonov1, A.M. Fedosseev1, Y.M. Kulyako2, S.A. Perevalov2, A.Yu. Shadrin3
Frumkin Institute of Physical Chemistry and Electrochemistry of RAS, 2Vernadsky Institute of Geochemistry and Analytical
Chemistry of RAS, 3Open joint-stock company VNIINM, Moscow, Russia, [email protected]
1
The hydrolytic behavior of uranyl ions have been studied in reducing media at elevated temperatures under
hydrothermal conditions. Hydroxylamine and hydrazine were used as reductants. Application of the first
one does not give complete reduction of uranium to tetravalent state, whereas the presence of the last one in
the system leads to full its reduction and complete uranium isolation from the solution as well-crystallized
UO2. It was found that moderate heating of nitrate solutions of U(VI), Np(IV-VI) and Pu(IV) in the presence
of hydrazine leads to formation of homogeneous mixture of hydrated dioxides of these elements (U, Np,
Pu)O2·nH2O, which on following heating up to ∼300ºС in air turn into crystalline product of
UO2, NpO2 and PuO2 solid solution. No crystalline U3O8 was found in this solid solution after its calcination
at 800ºC. Thus, even small molar part of Np and/or Pu relative to U in the initial mixture is able to stabilize
final dioxide phase. This technique of preparation of solid solutions U-Pu dioxides looks like as promising,
simple and effective way for MOX-fuel production.
Fig.2 Thermal analysis of hydrated U, Np and Pu oxides (a) and X-ray diffraction pattern of the actinides
dioxides solid solution (b) after their heating in air atmosphere to 800ºC: UO2 (1), NpO2 (2), PuO2 (3).
134
Nuclear and Related Techniques
4th-INCC 2014 I 4th International Nuclear Chemistry Congress
CRYSTALLINE STRUCTURE AND OXYGEN STOICHIOMETRY OF THE
Ba0.50Sr0.50Co0.80Fe0.20O3-d POWDERS OBTAINED BY EDTA-CITRATE METHOD
MEASURED BY X-RAY AND NEUTRON DIFFRACTION
Everton Bonturim1, Nelson Batista de Lima1, Vera Lúcia Mazzocchi1, Carlos Benedicto
Ramos Parente1, José Mestnik Filho1, Emília Satoshi Miyamaru Seo1
Instituto de Pesquisas Energéticas e Nucleares IPEN-CNEN/SP, São Paulo, Brazil, [email protected]
1
The Ba0.50Sr0.50Co0.80Fe0.20O3 (BSCF) is a good candidate as an air electrode for Intermediate Temperature
Solid Oxide Fuel Cells (ITSOFC). Studies have shown that different synthesis methods may modify the
powder characteristics, such as: morphology, crystalline size and surface microstructure.1 The transport
properties and catalytic activity of BSCF are directly associated with the perovskite structure (ABO3) of
solid state conductors, increasing due to substitution of the A and/or B site, accompanied by the formation of
oxygen vacancies. Zhou et al. (2009) mentioned that the substitution of Sr2+ by Ba2+ may increase the oxygen
vacancy concentration, thus optimizing the composition of BSCF.2 The investigation of these parameters
is usually made by X-ray diffraction, obtaining important information such as the crystal structure, lattice
parameter and atomic substitution, among other characteristics of the studied material. The ionic conduction
of perovskite oxides occur due to oxygen vacancy in the lattice structure of material.3
The results presented herein cover the crystal structure and oxygen vacancy of BSCF as characterized by
X-ray and Neutron Diffraction with the Rietveld refinement method. In the quest for the improvement of the
characteristics and properties of Ba0.50Sr0.50Co0.80Fe0.20O3-δ, a method of synthesis using a pair of complexing
agents as EDTA-citrates was used. The main phase was identified as having a cubic perovskite structure
with a = 3.9857 Å, without the presence of secondary phases. A theoretical density of 5.476 g.cm-3 hasbeen
achieved for BSCF calcined at 900 °C for 5 h. The results obtained by Neutron Diffraction confirm the
occupancy oxygen refined at 0.818 and the calculations for oxygen stoichiometry at 2.454. These results
showed oxygen vacancies, the most important feature for the performance of this compound when used as
cathodes in ITSOFCs.
REFERENCES
1) H. PATRA, et al. Powder Technol. 209 (2011) 98-104.
2) W. ZHOU, R. RAN, J. Z. SHAO, J. Power Sources. 192, 231-246 (2009).
3) T. ITOH, et al. Phys. B, 405 (2010) 2091-2096.
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
EVALUATION OF A 99mTc COMPLEX AS AN OIL MULTIPHASE RADIOTRACER
Martha Sahylí Ortega Pijeira1, Judith DOMÍNGUEZ1, Jorge L. BATISTA1, Yuniel TEJEDA1,
Ernesto Martínez Baez1, Jorge Borroto Portela1
Department of Radiochemistry, High Institute of Applied Sciences and Technologies, Havana, Cuba, [email protected]
1
Tracers obtained by radioisotope generators have been recognized as an attractive option for using radiotracer
technique at any industrial investigation site1. However, in most of the cases, it is necessary to adapt the
radioisotope obtained before using it. Extraction with the mixture Tributylphosphate (TBP) -Trioctylamine
(TOA) / Cyclohexane has been successfully used to adequate the 99mTc, eluted from 99Mo/99mTc generator, in
order to get an organic fluid radiotracer2. However, to carry out multiphase flow applications, it is essential
to test the 99mTc complex stability into the radiolabeled organic phase. Crude oil and water come together
from reservoir and remain like this along several stages of oil industry.
In this work, the influences of stirring time and 99mTc radioactive concentration on extraction process were
studied. 99mTc complex stability in crude oil in contact to saline waters was also evaluated.
Experimental results suggest that this technetium complex may be a suitable oil radiotracer for multiphase
petroleum related applications, which involved saline water.
REFERENCES
1) IAEA, Radiotracer generators for industrial applications (2013).
2) J. Domínguez, Y. León, A. Abreu, R. Gamboa, J. Borroto, Nucleus, 51 (2012) 26.
138
4th-INCC 2014 I 4th International Nuclear Chemistry Congress
VARIATIONS ON UO2-DOPED AND UNDOPED FUEL PELLETS MICROSTRUCTURES
BY THE ADDITION OF RECYCLED MATERIAL
Diogo Ribeiro Costa1, Franciole José Ezequiel1, Rodrigo Aparecido Barbosa1, João Paulo
Rodrigues Carnaval1
1
Brazilian Nuclear Industries (Indústrias Nucleares do Brazil S.A.– INB), Resende, Brazil, [email protected]
The effects of recycled material (U3O8) on microstructure of UO2-doped and undoped fuel pellets have been
investigated. The U3O8 powder was obtained by oxidation of a mix of defected pellets and grinding sludge,
at 380°C in air atmosphere, for 20 h. The UO2 powder was produced at Brazilian Nuclear Industries (INB)
by commercial AUC route. Two tests were carried out: the first one (“Z” tests) using only UO2 powder,
aluminum distearate (0.2 wt%) and dopants (by doping technology1); and the other one (“M” tests), adding
U3O8 (12 wt%) to the last blends. Samples of 0.1-0.5 wt% (gMetal/gU) of Al2O3, Nb2O5 and Cr2O3, and also
the undoped pellets, were manufactured in a laboratory press machine and then sintered at 1760°C for 5.7h
in a commercial sintering furnace, under wet hydrogen atmosphere.
The sintered densities values showed that 12 wt% of U3O8 decreased the densities by about 0.20 g/cm3 by
each 0.1 wt% of dopants addition in all three doping M tests. Regarding the grain growth behavior, the
undoped-pellets average values were 12.5 μm (without U3O8 and additives) and 9.5 μm (with U3O8 and
without additives). The values for the UO2-doped pellets in Z tests were enhanced with the addition of niobia
(up to 29.3 μm) and chromia (up to 36.0 μm), and a slight increase with alumina addition (up to 14.1 μm).
When U3O8 where added, these values were changed. The M tests maximum average results were 19.5 μm
for niobia (0.5 wt%), 28.3 μm for chromia (0.3 wt%) and 10.5 μm for alumina (0.3 wt%).
The results showed clearly that the U3O8 decreased, in all undoped and doped experiments, the average
values of both sintered density and grain growth. These behaviors are mainly owing to the lower sinterability
of the mix powder with U3O8 (lower specific surface area)2.
REFERENCES
1) S. J. Lee, D. H. Jung, C. Y. Lee, J. I. Kim, K. L. Jeon, J. R. Lee, J. H. Yang, K. S. Kim, 2011 Wat. React. Fuel Perf. Meet.
Paper ID T1 (2011) 016.
2) K. W. Song, K. S. Kim, Y. M. Kim, Y. H. Jung, J. Nuc. Mat. 277 (2000) 123.
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
HETEROGENEITY EVALUATION OF UO2 PELLETS TO BE USED IN A BRAZILIAN
MEASUREMENTS SYSTEMS INTERCOMPARISON PROGRAMS
Bárbara Fernandes Gonçalves Cristiano1, José Ubiratan Delgado1, José Wanderley S. da
Silva1, Aline Gonzalez Viana1, Fábio Cordeiro Dias1, Marcos Sodre Grund1, Ricardo Tadeu
Lopes1
Comissão Nacional de Energia Nuclear (CNEN), Instituto de Radioproteção e Dosimetria (IRD/CNEN), Rio de Janeiro, Brazil,
[email protected]
1
The Brazilian nuclear facilities must dispose of measurement systems that allow the determination of their
nuclear material inventories1. The main goal of this work is the characterization of enriched uranium dioxide
(UO2) pellets to use as reference material to evaluate and verify these systems through the participation
of the involved laboratories in intercomparison programs. The programs are formed by a network of
specialized laboratories in determining the material the nuclear fuel cycle. Therefore, before being sent
to collaborative laboratories, pellets from two different batches had their homogeneity confirmed and
their values with uncertainties estimated2. The heterogeneity evaluation was carried out in the Safeguards
Laboratory (LASAL) of Brazilian Nuclear Energy Commission (CNEN) through Destructive Analysis (DA)
and Nondestructive Analysis (NDA) techniques that are Davies & Gray/NBL titrimetric method3,4 and high
resolution gamma-ray spectrometry method5, respectively. Both techniques are used, routinely, for control
and accounting of the nuclear materials. The DA results were evaluated by one-way Analysis of Variance
(ANOVA), which allowed the calculation of between and within bottle homogeneity. The within bottle
homogeneity cannot be evaluated in NDA results. Student’s t-test with 99 % confidence level was used as an
alternative heterogeneity evaluation. No statistical significant differences were observed and both batches
are considered homogeneous. Thus, the UO2 pellets can be used in an independent Brazilian measurement
systems evaluation program.
REFERENCES
1) Comissão Nacional de Energia Nuclear, CNEN-NN-2.02, (1999).
2) Associação Brasileira de Normas Técnicas, ABNT ISO Guia 35 (2012).
3) A. R. Eberle, M. W. Lerner, C. G. Goldbeck, C. J. Rodden, NBL 252 (1970).
4) W. Davies, W. Gray, Talanta 11(1964) 1203–1211.
5) F. C. Dias, M. S. Grund, S. E. Smith, A. A. Solodov, INMM Annual Meeting (2007).
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CONCEPTION AND CONSTRUCTION OF A REMOTE PROBE FOR A PORTABLE
SPECTROMETER USING THE ENERGY DISPERSIVE X-RAY FLUORESCENCE
TECNIQUE
Francisco Antonio Brandão Junior1-2, Arno Heeren de OLIVEIRA1, Antonella LOMBARDI Costa1
Departamento de Engenharia Nuclear, Universidade Federal de Minas Gerais, 2Centro Federal de Educação Tecnológica de
Minas Gerais (CEFETMG), Belo Horizonte, Brazil, [email protected]
1
This paper presents a device that is an innovative complement of a portable spectrometer, based on the
use of NaI(Tl) cylindrical detectors and the energy dispersive X-ray fluorescence technique (EDXRF).
The innovative remote probe is composed by an optical fiber cable (Elgin-1,80 m, high definition), and
two aluminum cylinders, specially manufactured for optical junction purposes connected on its top ends.
Several advantages are obtained with the use of optical fiber in the detection system. The fibers have large
passband, small signal attenuation, immunity to electromagnetic interference and lower cost in relation to
the electrical cables. One side of the device is joined to a NaI(Tl) detector and the other side is connected
to a photomultiplier valve. The internal cylinder space is conical and dark painted and each one has an
adjustable system of converging lenses that focuses the beam sourced from the detector (fluorescence) on
the optical fiber, on which it travels through by total reflection, reaching the other extremity of the probe and
being focalized and distributed throughout the surface of the photomultiplier. This innovation simplifies the
detection system. This portable probe can bring new solutions for such kind of procedure, once it can reach
areas that the traditional device cannot access due to its lack of mobility and its external dimensions. The
first measurements and results of the tests obtained with the developed prototype were satisfactory and are
presented in this paper.
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METAL CONTAMINATION IN SOIL OF A SCRAPYARD OF IMPOUNDED VEHICLES
Camila Neves Lange1, Ana Maria Graciano Figueiredo1, Jacinta Enzweiler2
Instituto de Pesquisas Energéticas e Nucleares, IPEN- CNEN/SP, 2Instituto de Geociências, UNICAMP, São Paulo, Brazil,
[email protected]
1
Impounded vehicles scrapyard overcrowding has become a problem in many Brazilian cities. Brazilian law
states that the apprehended vehicles must not remain longer than 90 days in impound yard. However, in spite
of this, they remain longer than that and suffer from weathering action. As most of these areas do not present
an impermeable surface, superficial soil, ground water and superficial water are exposed to contamination.
Liquid residues by spill or by rain water leaching and particulate material by vehicle decomposition results in
diverse sources of pollution. The purpose of this study was to evaluate the concentration of potentially toxic
elements in superficial soils (0-20cm) inside the scrapyard of impounded vehicles of Ribeirão Pires-SP city.
Elemental concentrations were determined by X-ray fluorescence spectrometry. The results obtained were
compared with reference values established by the Environmental Protection Agency of the State of São
Paulo, the local regulatory environmental agency. The elements Cu, Mo, V and Zn presented concentration
values lower than the quality reference value (VRQ). The elements As, Cr, Pb and Ni showed concentration
levels higher than VRQ, and barium concentrations exceeded the prevention value (PV), the concentration
limit of a substance that causes no damage to soil and groundwater quality. Soil contamination was also
assessed by using the geoccumulation index (Igeo) and the enrichment factor (EF). Though elemental
concentration levels were not considered an environmental concern for certain elements, the Igeo for Cr
suggested moderate contamination, and EF for Ba and V indicated soil enrichment. These results suggest
anthropogenic influence, especially for Cr, and indicate a potential hazard to soil quality. For Ba and V, the
concentration patterns showed low correlation to other metals, indicating that these elements may be related
to the natural soil composition. The results of this study may be used to better understand soil contamination
on these sites for more effective environmental management.
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MEASUREMENTS STUDIES OF ACTIVITY AND GAMMA EMISSION
PROBABILITIES FOR 235U and 238U
Ronaldo Lins da Silva1, R. POLEDNA1, J. U. DELGADO1, Maria Candida Moreira de Almeida2,
R. N. ALVES3, J. S. ESTRADA3
Laboratório Nacional de Metrologia das Radiações Ionizantes, IRD, 2 Dinor, Comissão Nacional de Energia Nuclear -RJ,
Instituto Militar de Engenharia, Seção Eng. Nuclear, Rio de Janeiro, Brazil, [email protected]
1
3
The gamma-ray spectrometry was used to determine precisely the activity and gamma-ray emission
probabilities (Pγ`s) related to 238U and 235U decays in glass ampoule containers prepared by National
Laboratory of Ionization Radiation Metrology (LNMRI). A germanium spectroscopy system fitted with
appropriate voltage divider, combined with the use of radioactive mono-energetic and multi-gamma
standards and data adjustment programs, allowed to obtain measurements of activities and gamma emission
probabilities of these uranium isotopes with great accuracy.
In addition, proper placement of standards and samples relative to the top of the detector has significantly
reduced the influence of the correction factors for pile-up, attenuation and for losses due to gamma-gamma
and gamma-x coincidences.
Thus, the activity uncertainties obtained are 1.5 % to 235U and 1.7 % to 238U. Pγ’s of the most significant
energy for 235U and 234Pa (descendent of 238U) were determined and values for their uncertainties were lower
when compared with those found in the literature. The emission probability uncertainties are 1.3% to 235U
and 1.6% to 238U.
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Long-Term Performance Assessment of HPGe detectors used in the
Neutron Activation Analysis (LAN) of IPEN-CNEN/SP (Brazil)
Guilherme Soares Zahn1, Frederico Antonio Genezini1, Regina Beck Ticianelli1, Mitiko Saiki1
Instituto de Pesquisas Energéticas e Nucleares (IPEN-CNEN/SP), São Paulo, Brazil, [email protected]
1
In nuclear spectroscopy measurements, the performance of the radiation detectors employed is a key issue in
the final results; moreover, in comparative neutron activation analysis measurements, much of the method’s
simplicity depends on the stability of the detector between the measurements of the unknown and the
comparator, so that the detector’s efficiency can be effectively ruled out of the equation.
Due to the relevance of the detectors’ performances, LAN-IPEN have been performing daily verification
measurements in its operational detectors since 1999; this verification consists in the measurement of
composite (57-60)Co sources, in which the position, resolution and CPS (counts per second) for the 122 keV
peak of 57Co and the 1332 keV peak of 60Co are registered, along with the date and time of the measurement.
In this work, verification data for 11 HPGe detectors from two different makers and three different intrinsic
configurations were analyzed in respect to the efficiency stability (determined by the “arbitrary efficiency”
calculated by correcting the CPS for the isotope’s decay) and resolution for both peaks, as well as the ratio
between the efficiencies for 122 keV and 1332 keV. The results allow a discussion about the stability of
these parameters over time (in some cases, almost 15 years), their sensitivity to imminent detector failures
and their performance after a failure has been corrected; moreover, the results show a clear correlation
between the maker or configuration and the long-term performance of the detector.
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NATURAL RADIOACTIVITY IN WALL PAINTS: PRELIMINARY RESULTS
Leandro Milhomens da Fonseca1, Brigitte Roxana Soreanu Pecequilo1
Instituto de Pesquisas Energéticas e Nucleares, São Paulo, Brazil, [email protected]
1
Naturally occurring radionuclides with half-lives of the same order that the age of the earth, like 40K and the
radionuclides from the 238U and 232Th series, are the major source of exposure for mankind. Buildings and
houses are very important in human life , cause quite a lot of the lifetime is spent at home and / or office .
Virtually, every building material contains the natural radionuclides 226Ra , 232Th and 40K . Knowledge of the
levels of natural radioactivity in building materials is important for the assessment of population exposure to
natural radioactivity, since most passes 80 % of your life in the residences. 238U is 99.27 % of natural uranium
that is found throughout the earth’s crust in the form of uranium and trace amounts in all kinds of rocks and
minerals. Thorium is found in many rocks and soils with 100% 232Th. Several studies have been conducted
to evaluate natural radioactivity in building materials such as rocks , granites , marbles , sand , etc., however,
to date, there are no studies concerning the natural radioactivity that eventually the wall paints used internal
or externally in buildings and houses used could contain. The wall paints, as others construction materials,
has natural radionuclides originated from the mineral compounds used in its manufacturing process. The
titanium dioxide used as the white pigment in paints, is produced from the processing of ilmenite minerals,
representing 92% of the world demand of titanium minerals. As monazite, the main ilmenite radioactive
contaminant, contains 1 to 20% thorium dioxide and also some uranium traces, it is easy to assume that
wall pains could contain radioactivity. In this work, the activities concentrations of several wall paints will
be evaluated in order to assess possible incremental exposures of workers and the public. Nowadays, seven
wall paint samples were already analyzed. Each sample was tightly sealed in 100 mL HDPE flasks with a
plan screw cap and bubble spigot and measured during 150 ks with an extended range HPGe detector of
35% relative efficiency, after approximately 4 weeks resting, in order to ensure secular equilibrium. The
acquired spectra were analyzed using the InterWinner 6.0 software. The activity of 40K was calculated
through its single gamma transition of 1461 keV. The activity of 226Ra was determined by the weighted mean
of the 214Pb and 214Bi gamma transitions and the activity of 232Th by the weighted mean of the 212Pb, 212Bi and
228
Ac gamma ray transitions. The activities concentrations of the natural radionuclides varied from 3.13 ±
0.21 up to 14.1 ± 0.5 Bq/kg for Ra-226; from 5.9 ± 0.3 up to 46.0 ± 1.5 for Th-232 and from 6.9 ± 2.4 up to
195 ± 28 for K-40. Further, the study will be extended to a larger number of wall paints brands available in
Brazil and eventual radiological consequences of absorbed dose will be assessed.
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USE OF ICP-MS FOR DETERMINATION OF URANIUM AND THORIUM IN SOIL
SAMPLES
Helena Eugênia Leonhardt Palmieri1, Sarah Andresa Bonfim2, Fernanda José Augusto
Ferreira2
Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN), 2Bolsista de Iniciação Científica CDTN/CNEN, Belo
Horizonte, Brazil, [email protected]
1
Thorium and uranium occur naturally in soil, at concentrations that depend on the parent material from
which the soil was formed, the processes of formation, and the composition and the proportion of the
components of its solid phase. Quantifying these concentrations is important for environmental studies of
soil contamination and pollution, and choosing the methods for doing so is a key step in establishing these
heavy metal contents in soil samples.
We evaluated two digestion methods, one employing two-step microwave acid digestion and another using
that outlined by Ardini et. al.[1]. Certified Reference Materials (San Joaquim soil 2709 and AIEA SL-1)
were used as a quality control standard to validate the applied analytical procedure. The instrument used
for all determinations was Perkin Elmer ELAN DRC-e with seaspray nebulizer, cyclonic spray chamber, Ni
cones and quadrupole analyzer.
The results obtained for the total amounts of Th and U in the Certified Reference Materials were in satisfactory
agreement with the certified values for the two digestion methods.
REFERENCES
1) F. Ardini, F. Soggia, F. Rugi, R. Udisti, M. Gotti, Analytica Chimica Acta 678 (2010) 18-25.
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EXPERIMENTAL DESIGN APPLIED FOR THE OPTIMIZATION OF INAA METHODS
Robson Petroni1, Edson Gonçalves MOREIRA1
Instituto de Pesquisas Energéticas e Nucleares, IPEN - CNEN/SP, Osasco, Brazil, [email protected]
1
In this work 2k experimental design was carried aiming the multivariate optimization of INAA methods.
Three important factors of the measurement process were investigated: sample decay time (A), sample
distance to detector (B) and measurement time of radionuclide activity in the sample (C). Possible nuisance
factors, as sample mass (150 ± 10 mg), sample and standard geometry (10 mm x 8 mm x 1 mm), irradiation
time (8 hours) and thermal neutron flux (0.5 to 1.0 1013 cm-2 s-1) were controlled and considered as constant
terms for all experiments of the 23 experimental design matrix. Two multielemental methods of Neutron
Activation Analysis Laboratory (LAN, IPEN – CNEN / SP) had its factors studied: a first for determination
of the total mass fraction of Cr, Co, Fe, Rb, Sc, Se and Zn in biological matrix samples and a second for
determination of the total mass fraction of Cr, Co, Fe, Sc and Zn in geological matrix samples. Three
replicate analyses for each experiment were carried out aiming to estimate the individual contribution of
selected factors in the final mass fraction results. Optimized conditions for each method were outlined by
means of accuracy results (trueness and precision), main effects, interaction contrasts and counting statistics
uncertainty. According to the results, A and B factors presented the most significant contribution for the
optimization of INAA methods for most measurands. On the other hand, factor C does not present significant
influence on the final results.
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TDCR AND CIEMAT/NIST LIQUID CINTILLATION METHODS FOR 3H, 14C, 99TC AND
68
Ge/68Ga ACTIVITY STANDARDIZATION IN RADIONUCLIDE METROLOGY
Paulo Alberto Lima da CRUZ1, Carlos José da Silva1, Akira Iwahara1, Jamir dos Santos
Loureiro1, Antônio Eduardo de Oliveira1, Luiz Tauhata1, Ricardo Tadeu Lopes2
Instituto de Radioproteção e Dosimetria/Comissão Nacional de Energia Nuclear (IRD/CNEN), 2Programa de Engenharia Nuclear,
Universidade Federal do Rio de Janeiro (PEN/COPPE, UFRJ), Rio de Janeiro, Brazil, [email protected]
1
In this work are presented the TDCR (Triple to Double Coincidence Ratio) and CIEMAT/NIST methods
of the liquid scintillation technique implemented in most of National Institutes of Metrology as reference
methods for activity standardization of radionuclides which decay by beta emission and electron capture
decay. Currently, the TDCR method is the most recommended for direct absolute standardization of pure
beta emitters. The computer codes developed to calculate the detection efficiency take into account:
radionuclide decay schemes, beta decay theory, evaluation of the quenching parameter for electrons and
photons interactions with the scintillation cocktails molecules, Poisson statistic model, as well as Monte
Carlo simulation applied to photon interactions and detection system. Measurements were performed for
3
H, 14C, 99Tc, which are pure beta emitters in a large energy range, and 68Ge/68Ga which decay by positron
emission and electron capture, with uncertainties smaller than 1% (k=1). The 99Tc solution was obtained
from international BIPM (Bureau International des Poids et Mesures) key-comparison and the 68Ge/68Ga
standardization was also performed by LNHB/CEA/France radionuclide laboratory.
REFERENCES:
1)P. A. L. da Cruz, C. J. da Silva, D. S. Moreira, A. Iwahara, L. Tauhata, R. T. Lopes, Applied Radiation and Isotopes. 87
(2014) 175.
2)F. Rösch, Applied Radiation and Isotopes. 76 (2013) 24.
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BOVINE KIDNEY REFERENCE MATERIAL PREPARATION PROPOSAL TO BE USED
IN QUALITY ASSURANCE OF CHEMICAL MEASUREMENTS IN MEAT PRODUCTS
Liliana Castro1, Edson Gonçalves MOREIRA1, Vera Akiko MAIHARA1, Marina Beatriz Agostini
Vasconcellos1
Instituto de Pesquisas Energéticas e Nucleares – IPEN-CNEN/SP, SP, Brazil, [email protected]
1
Quality assurance of chemical measurements is a very important issue, because appropriately accurate
analytical information is a prerequisite for decision-making in many different areas of knowledge. The
comparability of measurement results is a key requirement for both international trade, which requires
that the necessary conditions for product certification and quality assurance measurements can be accepted
globally, and for the implementation of international environmental and public health regulations. The use
of reference materials is a fundamental tool in the achievement of this aim.
Focusing in the food production and consumption field, Brazil is the major exporter country of bovine meat
in the world. On the other hand, the consumption of bovine meat per capita in Brazil is in the second place
in the South American region.
Taking all this into account, it is evident the importance of preparing new reference materials with meat
matrix in Brazil, to ensure the quality and safety of the products consumed by the population, to support the
national industry and also to facilitate trade within the region.
In this context, a proposal for the preparation and certification of a new local reference material of bovine
kidney was elaborated. The concentration of major and minor elements will be determined, as well as some
parameters of nutritional interest as total fat and proteins.
The present work describes all the necessary steps to produce this material. Elements such as Ag, As, Ca,
Cd, Co, Cr, Cu, Fe, Hg, Mg, Mn, Na, Pb, Se and Zn will be analyzed by the methods of Neutron Activation
Analysis, NAA, and Atomic Absorption Spectrometry, AAS.
A test sample was prepared for a feasibility study and to test all the proposed steps. Some of the inorganic
constituents were determined in this test sample in concomitance with Certified Reference Materials and
the obtained results indicated the feasibility of the production and certification of the new kidney reference
material.
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ELEMENTAL DETERMINATION IN Canoparmelia texana LICHEN SPECIES USING
X-RAY FLUORESCENCE SPECTROMETRY
Rosiana Rocho ROCHA1, Mitiko Saiki1, Nemitala Added2, Frederico Antonio Genezini1
Instituto de Pesquisas Energéticas e Nucleares, IPEN-CNEN/SP, 2Instituto de Física - Universidade de São Paulo, São Paulo,
Brazil, [email protected]
1
It is well known that large cities are affected by atmospheric pollution caused by vehicular emissions,
urbanization and industrial activities. Presently, there is a growing need to evaluate air quality and the
levels of pollutant emissions since they can affect the general health of the urban population. In most cases
air quality is assessed by direct measurement by using collectors which in turn makes the air monitoring
expensive and difficult for large urban areas like São Paulo city. An alternative method is the use of plants
as biomonitors to evaluate air pollutants and their correlation to urban health problems. The aim of this
study was to evaluate the viability of assessing pollutant levels by analyzing lichens by X-ray fluorescence
spectrometry (XRFS). Canoparmelia texana lichen species were collected from tree barks in different sites
of the Campus of the São Paulo University. In the preparation for analysis, lichen samples were cleaned,
washed with water, freeze dried and ground. The resulting powdered lichen samples were compressed into
cylindrical pellets with diameter of 1cm for XRFS measurements. The concentration of identified elements
can be classified in different levels: Ca, K and S were found at the levels of percentage; As, Br, Cl, Cu, Fe,
Mn, Rb, Sr and Zn at the mg kg-1 levels and the elements Cr at low level of μg kg-1. For quality control of
the results certified reference materials (IAEA Lichen 336 and INCT Mixed Polish Herbs) were analyzed
and the comparison resulted in values of |z score ≤ 2. The low detection limit (DL) achieved in the XRFS
setup for most elements allowed a reliable determination of the concentrations found in the lichens. These
findings showed that analysis of lichens using XRFS technique can be used to air pollution in large urban
areas as well as in remote areas where there is no monitoring network.
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DOSIMETRIC STUDY FOR IRRADIATION PROCESSING OF CHESTNUT FRUITS:
EXPERIMENTAL SETUP AND DOSE VALIDATION
Amilcar Lopes Antonio1-2-3, Isabel C. F. R. Ferreira1, Albino Bento1, M. Luisa Botelho2,
Begoña Quintana3
CIMO/ESA, Instituto Politécnico de Bragança, 2Centro de Ciências e Tecnologias Nucleares, IST, Universidade de Lisboa,
Departamento de Física Fundamental, Universidad de Salamanca, Bragança, Portugal, [email protected]
1
3
Food irradiation is being used as a feasible alternative in several countries for insects’s disinfestation, food
decontamination or to increase shelf-life1. Therefore our research group developing studies for the preservation
of European varieties of chestnut fruits by gamma and e-beam irradiation, reporting its positive influence
in some bioactive compounds2,3. During irradiation, the estimated dose is usually monitored with routine
dosimeters (previously calibrated by standard dosimeters), to assure the desired effects without compromise
the main food characteristics, namely color or texture and nutrients composition. In an experimental gamma
irradiation chamber with four Co-60 sources and the dimensions of 20x50x65 (WxLxH), a square box of
PMMA (polymethylmethacrylate) 15x15x7 cm was positioned inside the chamber, in the 2nd level of an
aluminum support built for the effect. The irradiation dose in the box was estimated for different media with
three independent dosimetric systems. A standard dosimeter; ionization chamber; a reference dosimeter,
liquid chemical Fricke dosimeter; and a routine dosimeter, Amber Perspex, were used to estimate the dose
in a media with different densities: air, water and chestnut fruits. For Amber Perspex dosimeters it was also
possible to build a phantom with the dosimeter inside the fruit. With those results it was possible to elaborate
a dose mapping of the irradiation box, estimating the dose, dose rate and dose uniformity ratio (Dmax/Dmin).
The results were validated comparing the experimental estimated doses obtained with the three dosimetric
systems and using a state-of-art simulation program for radiation interaction with matter4. With the isodose
maps we can predict the doses and design an irradiation process to irradiate the samples, with or without
rotation, to get a better dose uniformity. The results also shown that the dose uniformity ratio obtained is in
conformity with the good practices for food irradiation.
Acknowledgments
Foundation for Science and Technology, Portugal (Project FCT-RECI/AAG-TEC/0400/2012).
REFERENCES
1) A. L. Antonio, M. Carocho, A. Bento, B. Quintana, M. L. Botelho, I. C. F. R. Ferreira, Food Chem Toxicol 50 (2012)
3234–3242.
2) A. L. Antonio, A. Fernandes, J. C. M. Barreira, A. Bento, M. L. Botelho, I. C. F. R. Ferreira, Food Chem. Toxicol. 49 (2011)
1918–1923.
3) M. Carocho, A. L. Antonio, J. C. M. Barreira, A. Rafalski, A. Bento, I. C. F. R. Ferreira, Food Bioprocess Tech (2013)
September.
4) S. Agostinelli et al, Nucl. Instr. Meth. Phys. Res. 506 (2003) 250–303.
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Evaluation of Cl, K, Mg, Mn and Na in food groups of São Paulo
Total Diet
Jéssica Braga Ambrogi1, Roseane Pagliaro Avegliano1, Uanda Paula de Medeiros dos Santos1,
Vera Akiko MAIHARA1
Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), São Paulo, Brazil, [email protected]
1
The objective of this study was to evaluate dietary intake of Cl, K, Mg, Mn and Na to Total Diet Study (TDS).
This TDS is an approach based on the evaluation of food samples representing foods consumed by the São
Paulo state population. The combination of the data obtained by analysis in laboratory and individual daily
consumption data by national surveys result in an estimate of the dietary intakes of these elements. Two
Brazilian Total Diet Study experiences to provide measurement of elements by INAA have been developed
by Neutron Activation Laboratory at the IPEN/CNEN SP. As of present there are no previous experiences
in Brazil using Total Diet. Compared to the 1st Brazilian TDS1 performed in 2005-2009, the current 2nd TDS
has shown more accurate results. While the first one was concerned to foods which were acquired by the
population for household consumption, the second TDS includes foods consumed both inside and outside
of the household resulting in a total daily consumption of the population. The source of data for the 2nd
TDS was based on the Household Budget Survey (POF 2008-2009) conducted by the Brazilian Institute of
Geography and Statistics. The foods with similar nutritional composition were grouped, resulting in 19 food
groups. The concentrations of Cl, K, Mg, Mn and Na were determined in the 12 food groups from the List
Food of the 2nd TDS by Instrumental Neutron Activation Analysis. These elements were determined after
irradiations for 20 seconds at a neutron flux of 1012 n cm-2 s-1 in the pneumatic system of the IEA-R1 nuclear
research reactor of the IPEN-CNEN/SP. The results showed that the dietary intake values of these elements
were comparable to the first TDS.
REFERENCES
1) R.P.Avegliano, V.A.Maihara, F.F.da Silva,J. Food.Compos.Analys. 24 (2011) 1009.
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Preliminary archaeometric study of the archaeological site of
Lapa Grande de Taquaraçu
Diego Renan Giglioti Tudela1, Astolfo G. M. Araujo2, Sonia Hatsue Tatumi3, Juan C. R.
Mittani3, Casimiro S. Munita1
Instituto de Pesquisas Energéticas e Nucleares (IPEN–CNEN/SP), 2Museu de Arqueologia e Etnologia, Universidade de São
Paulo (USP), 3Universidade Federal de São Paulo (UNIFESP), São Paulo, Brazil, [email protected]
1
There are few archaeometric studies in the literature that compare sediments found in archaeological sites
with archaeological ceramics. Nevertheless, the study of sediments found in a household (cooking and
occupation) may aid in understanding the human occupation and addressing the location and identification
of specific activities and function. This paper includes the analysis of 60 sediment samples from the Lapa
Grande de Taquaraçu archaeological site by instrumental neutron activation analysis, INAA, in which were
determined the concentrations of Ce, Co, Cr, Cs, Eu, Fe, Hf, K, La, Lu, Nd, Rb, Sc, Sm, Ta, Tb, Th, U, Yb
and Zn. The site is located in the municipality of Jaboticatubas, 60 km from Belo Horizonte, Minas Gerais
state, Brazil. The data set was studied using cluster analysis, principal component analysis and discriminant
analysis, and Procrustes analysis. The study showed three different compositional groups that represent the
fluvial environment and the deposition in the household. Samples of each group were analyzed by means of
X-ray diffraction, XRD, and the results showed that there are differences in the crystalline phases.
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ARCHAEOMETRIC STUDIES OF CERAMICS FROM THE SÃO PAULO II
ARCHAEOLOGICAL SITE
Rogério Baria RIBEIRO1, Nilo F. CANO1, Shigueo Watanabe2, Sonia Hatsue Tatumi3, Eduardo
Góes Neves4, Casimiro S. MUNITA1
Instituto de Pesquisas Energéticas e Nucleares, IPEN-CNEN/SP, 2Instituto de Física, Universidade de São Paulo, 3Universidade
Federal de São Paulo, 4Museu de Arqueologia e Etnologia, Universidade de São Paulo, SP, Brazil, [email protected]
1
The artifacts found in archaeological sites are related to ancient people who lived there long ago. The more
abundant and important artifacts found in many areas worldwide are ceramics which combine, in the most
part, durability with ubiquity. Several analytical methods including the nuclear and non-nuclear analytical
methods are important tools for the characterization of archaeological materials and influence preservation
and restoration. From the chemical and physical analyses, it is possible to infer technical processes in
archaeological ceramics. This paper aims at studying the elementary chemical composition of 70 ceramic
fragments from the São Paulo II archaeological site. The site is located along the Solimões river, next to Coari
city in the Brazilian Amazon. The characterization was performed using instrumental neutron activation
analysis, INAA, in which were determined the concentration of Ce, Co, Cr, Cs, Eu, Fe, Hf, K, La, Lu, Na,
Nd, Sb, Sm, Rb, Sc, Ta, Tb, Th, U, Yb and Zn in the samples. The Mahalanobis distance was used to study
the presence of outliers. The concentration data was studied next using multivariate statistical methods,
such as cluster analysis, principal component analysis and discriminant analysis. The results showed three
different chemical groups of samples regarding the similarity/dissimilarity between samples. Ceramics from
each group have been selected and dated using thermoluminescence, TL. The ages of the samples varied
between 895 ± 92 and 1142 ± 100 A.D. Electron paramagnetic resonance, EPR, was used to determine the
firing temperature. The firing temperature varied between 600 ± 50 to 650 ± 50°C. The results found in this
study are consistent with other works conducted in the Central Amazon.
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SPATIAL DOSE DISTRIBUTION IN A SYNTHETIC BREAS ON A THORAX PHANTOM
INDUCIED BY SODIUM PERTECNETATE-99mTc (Na99mTcO4-) SILICON BALLON
Carla Flávia de Lima1-2, Tarcisio Passos Ribeiro de Campos1
Programa de Ciências e Técnicas Nucleares do Departamento de Engenharia Nuclear, Escola de Engenharia, Universidade
Federal de Minas Gerais, 2Ecograf – Núcleo de Diagnóstico Cardiovascular S/C Ltda, Belo Horizonte, Brazil, carla.flavia@terra.
com.br
1
Breast cancer is the most frequent malignant neoplasm in women, especially after age of 50, ranking first
in developed countries1,2. It is the fifth cause of death worldwide and the third in Europe, after lung and
colorectal cancer, causing half million deaths every year1,3. The use of radiotherapy as a component of breastconserving therapy or after mastectomy has been proven to reduce the risk of loco-regional recurrence and
improve long term breast cancer specific and overall survival4. Despite of that, it is necessary to improve the
radiation therapy doses on the tumor in situ, reduce the collateral effects from the treatment and make medical
expanding lower. A silicon balloon was placed internally in the left synthetic breast of a thorax phantom
at the lateral superior quadrant of the armpit. A radiochromic film of 10 x 10 cm was affixed on near the
balloon in the sagittal direction, having the balloon centered. The balloon was filled with 3 mL of 25.9 GBq
(700 mCi) of Na99mTcO4- and held by 24 h (4 T1/2). The radiochromic film was sensitized, removed. After
the irradiation, the sensitized films was digitalizes at scanner of transmission HP. The program ImageDIG
and ImageJ were used to decompose each image in its components R and G. The data had been analyzed
based on the intensity of Red and Green components, RGB (Red, green, blue). A calibration curve was used
to convert optical density from the film on absorbed dose. So, spatial dose distribution was generated. The
results shown that the application Na99mTcO4- implies high dose in the breast tissue adjacent to the tumor
and preserves vital structures adjacent. In conclusion, the balloon presents itself as a viable option for the
adjunctive treatment of breast cancer in patients who have appropriate indication. Irradiation with sodium
Na99mTcO4- generates high doses in breast tissue and consequently in the tumor bed. This treatment has low
cost, availability and reduced time of treatment, decreasing the side effects of conventional radiotherapy.
REFERENCES
1)P. Boyle, B. Levin (eds), World Cancer Report 2008 (Internet Monography), 2008, http://www.iarc.fr/in/publications/pdfs.
online/wcr/2008/wcr_2008.pdf (acessed 12.05.14)
2)M. Lippman, Cáncer de mama, in: A.S. Fauci, E. Braunwald, D.L. Kasper, S.L.Hauser, D.L. Longo, J.L. Jameson, et al.
(eds), Harrison Principios de Medicina Interna (Internet Monography), 17th ed. Mc Graw Hill Medical, Columbus, 04, 2009,
http://www.harrisonmedicina.com/content.aspx?a1D=3716764&searchStr ncer+colorrectal (acssed 12.05.14)
3)J. Ferlay, P. Artur, M. Boniol, M. Heanue, M. Colombit, P. Boyle, Estimates of the cancer incidence and mortality in Europe
in 2006, Ann. Oncol. 18(2007) 581-529
4)J.D. Schoenfeld, J.R. Harris, Abbreviated course of radiotherapy for breast cancer, The Breast 20(20111) S3, S116-S127.
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INORGANIC ELEMENTS IN SUGAR SAMPLES CONSUMED IN SEVERAL
COUNTRIES
Paula Maria Borges de Salles1, Maria Ângela de Barros Correia Menezes2, Tarcisio Passos
Ribeiro de Campos1
Universidade Federal de Minas Gerais (UFMG), Departamento de Engenharia Nuclear (DEN), 2Centro de Desenvolvimento da
Tecnologia Nuclear/Comissão Nacional de Energia Nuclear (CDTN/CNEN), Serviço de Reator e Técnicas Analíticas (SERTA),
Belo Horizonte, Brazil, [email protected]
1
Sugar is considered a safe food ingredient1, wherein the optimal consumption should be around 10 to 15
kg/person/year2. However, it can be contaminated by inorganic elements during its production process2,3,4.
Therefore, this study aimed at checking the presence of inorganic elements in samples of crystal, refined
and brown sugar available for consumption in several countries. To determine the chemical elements, it
was applied the cylindrical 5g-sample methodology5 by neutron activation technique, k0-method, using
the TRIGA MARK I IPR-R1 reactor located at CDTN/CNEN, in Belo Horizonte. Several essential and
non-essential elements – probably toxics – were analysed in a large range of concentrations. Therefore, As,
Br, Ca, Co, Cr, Cs, Fe, Hf, K, Na, Rb, Sb, Sc, Se, Se, Sr and Zn were determined in the samples of crystal/
refined and brown sugar and the aditional presence of Au, La and Sm in brown sugar samples. The results
are discussed comparing to maximum values foreseen in the international and Brazilian legislations.
REFERENCES
1) M. D. Ioannidou, G. A. Zachariadis, A. N. Anthemidis, J. A. Stratis. Talanta 65 (2005) 92.
2) A. I. Ismail, J. M. Tanzer, J. L. Dingle. Community Dentistry and Oral Epidemiology 25 (1997) 438.
3) P. Blasser, P. Iasser, L. J. Zimermann, W. Shotyk. Science of Total Environment 249 (2000) 257.
4) L. Ramos, M. A. Fernandez, M. J. González, L. M. Hernandez. Bull Environmental Contamination and Toxicology 63 (1999)
305.
5) M. A. B. C. Menezes, R. Jaćimović. J Radioanal Nucl Chem 300 (2014) 523.
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MEASUREMENTS OF TRACE ELEMENTS IN VOLCANIC LAVAS
Pedro Vinicius Guillaumon1, Eric B Norman2, Keenan J Thomas2, Paulo R Pascholati1,
Tufic Madi Filho1, Iuda D Goldman vel Lejbman1
Universidade de São Paulo, 2University of California at Berkeley, São Paulo, Brazil, [email protected]
1
We have used neutron activation analysis to measure the abundances of approximately 33 different elements
in lava samples collected from three different Hawaiian islands, from Mt. Kilimanjaro, Mt. Etna, Rwanda,
Uganda, India, Ecuador, and Iceland. Neutron irradiations were performed at the McClellan Nuclear
Radiation Center and IPEN and gamma-ray counting was done at McClellan, UC Berkeley, LBNL, and
IFUSP using large-volume high-purity Ge detectors, anti-coincidence and coincidence techniques. Results
demonstrate that the measured elements are present with large differences between samples. Particularly
the thorium and uranium abundances are more than 10 times higher in the Kilimanjaro than in the other
samples. Results from the measurements will be presented and comparisons will be made between the traceelement compositions of the lavas from these different sites, with special emphasis on the abundances of
thorium and uranium.
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QUALITY ASSESSMENT OF THE FLUOXETINE DRUG MANIPULATED IN THE
CITY OF BELO HORIZONTE, BRAZIL
Alexandre Soares Leal1, Fernanda Peixoto Sepe1, Tatiana Cristina Bomfim Gomes1, Mitiko
Saiki2
Centre for Development of Nuclear Technology (CDTN), Brazilian Commission for Nuclear Energy (CNEN), 2Nuclear and
Energy Research Institute (IPEN), Brazilian Commission for Nuclear Energy (CNEN), Belo Horizonte, Brazil, [email protected]
1
In this work, the Fluoxetine, a drug largely used in the treatment of depression and other psychiatric
illnesses commercialized by the pharmacies of manipulation in Belo Horizonte, Brazil, was analysed by
neutron activation analysis, (NAA), by the Institutes CDTN, using the k0-INAA method, and by the IPEN,
using the comparative method. These analyses aimed to obtain complementary data about the quality of the
manipulated Fluoxetine to a survey carried out by the State Health Surveillance Agency of Minas Gerais,
Brazil (VISA/MG)1 and to determine the presence of impurities in order to perform a preliminary study of
the heterogeneity of the samples from each pharmacy. Due to operational reasons, the institutes analysed
different set of samples. The results pointed out the presence of: Al, As, Au, Br, Ce, Cl, Co, Cr, Hf, La, Sb,
Sc, Sm, Th and Zn. These elements may be originated from the raw material, imported from other countries.
Elements such as Cl, Fe, K, Mg and Na could be expected in this kind of samples because they are normally
present in the substances used as excipients in the preparation of the medicines.
REFERENCES
1) A. S Leal, F. P Sepe, T. C. B. Gomes, A. S. Santana, L. H. Cunha, M. Saiki, Rev. VISA em Debate 2 (2014) 1.
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CYCLOTRON PARAMETERS FOR C-11 YIELD
Gustavo Lobato Campos1, Tarcísio Passos Ribeiro de Campos1
Escola de Ciências e Técnicas Nucleares, Universidade Federal de Minas Gerais, Nova Lima, Brazil, [email protected]
1
The importance of cyclotrons has been growing over few early years in Brazil, specially to produce
radioisotopes for nuclear medicine. Short half-life radionuclides, as carbon-11 (t1/2=20.4 min), are of interest
as precursor of many radiophamaceuticals; however, the very short half-life limits its general application on
all Brazilian territory. So there are common recent trend for developing a compact, efficient, and low cost
accelerator capable to operate in all medical centers. There are many engineering aspects for designing a
cyclotron for radioisotopes production. Feasibility of nuclear reaction by cross-sections is one of the most
important1, and consequently the nuclear reaction rates at the target. Herein, the research focus addressed
the yield production of C-11 radioisotope in order to define accelerator parameters. The aim is to establish
an arbitrary value of yield (at end of bombardment, EOB), and evaluate how accelerator parameters such as:
beam current and time of irradiation vary in according to the expected radioisotope yield after EOB. Data
from literature for carbon-11 1,2 was considered and applied as reference to the EOB activity equation. The
following variables: beam current or irradiation time can be predicted knowing the EOB activity,. A Matlab
algorithm was developed. Results were over 90% close to reference values, compared to those reported in
the literature. Cyclotron parameters for a specific yield of C-11 can now be known.
REFERENCES
1) Kenneth R. Buckley, Salma Jilvan, Thomas J. Ruth, Nuclear Medicine and Biology, 31 (2004) 825-827.
2) T. Vandewalle and C. Vandecasteele, Int. J. Appl. Radiat. Isot. 34 (1983) 1459-1464.
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NAA AND XRF TECHNIQUE SEDIMENT ASSESSMENT FOR MAJOR AND TRACE
ELEMENTS - TIETÊ RIVER, SÃO PAULO STATE, BRAZIL
Flávio R. Rocha1, Paulo S. Cardoso da SILVA1, Lucas M. Castro1, Sonia Maria Barros de
Oliveira2, Déborah I. T. FÁVARO1
Neutron Activation Analysis Laboratory (LAN/CRPQ), IPEN/CNEN, 2Geoscience Institut, São Paulo University, São Paulo,
Brazil, [email protected]
1
The Tiete River drains an area composed of six sub-basins (Alto Tiete, Sorocaba/Médio Tiete, PiracicabaCapivari-Jundiai, Tiete/Batalha, Tiete/Jacaré and Baixo Tiete). Along its extension (1,100 km), its margins
bathe 62 municipalities. In spite of all its historical contributions, hydroelectric potential and being one of
the most economically important rivers in the state of São Paulo, the Tiete River is also one of the world’s
most polluted rivers. As a result of pollution problems observed over the last few decades, the aim of
this study is to evaluate the concentration of some major and trace elements in surface sediment samples,
in 07 points from its headwaters in Salesópolis until Porto Feliz municipality, passing through the São
Paulo City Metropolitan Region (RMSP) where considerable amounts of industrial and domestic sewages
discharges occur. For this purpose, two nuclear analytical techniques were applied and their respective
elements analyzed were: INAA: As, Ba, Br, Ca, Co, Cr, Cs, Fe, Hf, Na, Rb, Sb, Sc, Ta, Th, U and Zn; XRF:
major elements and loss of ignition. The INAA results were compared to the NASC reference values (North
American Shale Composite) and regional basal values. The enrichment factor (EF) and geoaccumulation
index (GI), to assess the presence of anthropogenic pollution sources, were used. EF >2.0 were obtained for
the elements As, Hf and Zn for the points 04 to 07. At point 01, EF>5.0 were obtained for the elements Hf, Th
and U and decreasing to EF>3.0 until point 07. In addition, the concentration of dissolved oxygen (DO), pH,
conductivity and oxidation-reduction potential (ORP) in the sediment and water samples from all sampling
points were measured. The results indicated the water quality degradation along the sampling points: DO
varied from 8.5 at point 01(Tietê River headwaters) to 1.1 ppm at point 07 (Porto Feliz municipality);
conductivity from 34.8 to 430 µS cm-1 for the same points, with value of 690 at point 02 (Santana do
Parnaiba municipality) and ORP changing drastically from 230 at point 01 to -400 mV at point 02. From
the data of this study, it will be possible to diagnose the Tiete River sediment quality of the studied area.
These results may be used for future corrective actions as well as to avoid further damage to the quality of
this important river.
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4th-INCC 2014 I 4th International Nuclear Chemistry Congress
INVESTIGATION OF WEAR METALS IN BIOFUEL VEHICLES LUBRICATING OILS
BY ENERGY DISPERSIVE X-RAY FLUORESCENCE SPECTROMETRY
Rogério Alves de Sousa REIS1, Vera Lúcia Ribeiro Salvador1, Ivone Mulako Sato1
Instituto de Pesquisas Energéticas e Nucleares, IPEN - CNEN/SP, Embu das Artes, Brazil, [email protected]
1
Lubricating oils are used in engines to prevent the wear of moving parts and their main function is to reduce
friction, provide oxidation stability, promote internal cleansing and increase the durability of the equipment.
In the contemporary world, the amount of different types of vehicles has grown expressively; therefore, it
is vital to determine the wear metals in lubricating oils for the environmental pollution control, population
health prevention and, also, the engine evaluation in the automotive industry.
In this work, wear metals, such as Ca, V, Cr, Fe, Ni, Cu, Zn, Ag, Cd and Pb, in used lubricating oil from
biofuel cars, was determined by Energy Dispersive X-Ray Fluorescence spectrometry (EDXRFS). The used
lubricating oils sampling was carried out in an Authorized Car Dealer´s, as to type of fuel (gas, alcohol or
mixture users) and mileage. Also, unused oils from different labels were collected.
Two sample preparations were studied: direct analysis, i.e. in liquid form, placed in adequate sample holder,
where the X-ray analysis was performed without any sample preparation; and in layered form (thin film),
where 50µL of the sample was deposited onto Whatman No. 41 filter paper and dried under infra-red lamp.
For each group, a better instrumental condition analysis (atmosphere and measurement conditions) was
carried out.
Individual calibration curves were obtained from certified materials and evaluation of the method was made
using certified reference material.
Sensibility, quickness of analysis, precision and accuracy for each sample preparation are discussed.
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X-RAY FLUORESCENCE TECHNIQUES APPLIED TO CHEMICAL
CHARACTERIZATION IN PRESERVED WOODS (eucaliptus ssp)
Sergio Matias Pereira Junior1, Vera Akiko MAIHARA2, Edson Gonçalves Moreira2, Vera Lúcia
Ribeiro Salvador2, Ivone Mulako Sato2
Instituto de Pesquisas Tecnológicas de São Paulo - IPT, 2Instituto de Pesquisas Energéticas e Nucleares, IPEN - CNEN/SP, São
Paulo, Brazil, [email protected]
1
Due to its versatility, easy handling and mechanical properties, make this wood is a type of material comparable
to steel, concrete and polymeric materials, allowing its use in different applications. The chemical wood
preservatives aim to increase wood natural durability. The regulated wood preservative products are CCA
(chromated copper arsenate), CCB (copper chromium and boron salt) and CA-B (copper azole type B).
Brazil produces around 1.2 mi m³ of treated wood to meet the annual demand of the railway, electric, rural
and construction sectors. Analytical techniques, such as Flame Atomic Absorption Spectrometry (FAAS) and
Inductively Coupled Plasma Optical Emission Spectrometry (ICP OES) have been used for the evaluation
of wood preservative treatment processes.
X-Ray Fluorescence Spectrometry (EDXRF: Energy Dispersive X-Ray Fluorescence and PXRF: Portable
X-Ray Fluorescence) have been strongly recommended for wood treatment control process and wood waste
assortment by Forest Products Industry Technology Roadmap1.
In this work, the sapwood blocks samples, with the dimensions 3.0 cm x 3.0 cm x 2.0-3.0 cm (width x
length x thickness, respectively), were obtained from Eucalipstus ssp tree, and they were separated in five
groups. Five different concentrations of CCA solutions were applied, in order to obtain different retentions
(4.0, 6.5, 9.6, 12.8 and 17.0 kg of CCA/m³ sapwood). Cu, Cr and As contents were determined by EDXRF
and PTXRF, using the Fundamental Parameters method in treated sapwood blocks, directly without any
chemical treatment. The grounded treated sapwood samples were also analyzed by FAAS and Instrumental
Neutron Activation Analysis (INAA).
A comparative study of the results of the analytical methods was carried out and performance criteria such
as sensibility and accuracy are discussed.
REFERENCES
1)Agenda 2020 Technology Alliance, U.S. Department of Energy, American Forest & Paper Association Georgia Institute of
Technology, Forest Products Industry Technology Roadmap (2010), Georgia, United States of America.
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4th-INCC 2014 I 4th International Nuclear Chemistry Congress
CORROSION OF TiO2-COATED STAINLESS STEELS STUDIED BY
ELECTROCHEMICAL TESTS AND NEUTRON ACTIVATION ANALYSIS
Olandir Vercino Correa1, Mara Cristina L. de Oliveira2, Renato Altobelli Antunes3, Mitiko
Saiki1, Edval Gonçalves de Araújo4, Marina Fuser Pillis1
Nuclear and Energy Research Institute, IPEN-CNEN/SP, Materials Science and Technology Center, 2Electrocell Ind. Com.
Equip. Elétricos LTDA, 3Federal University of ABC (UFABC), 4Prest Vácuo Ltda, São Paulo, Brazil, [email protected]
1
Titanium dioxide (TiO2) thin films have received much attention due to a combination of attractive
engineering properties such as high corrosion resistance, hardness and wear resistance1. Enhancement
of surface properties is a must-attend issue for metallic components used in nuclear fuel reprocessing
plants as the failures associated the use of metallic alloys in this environment is a consequence of surface
degradation by corrosion and wear2. TiO2 films could be advantageously applied to protect stainless steels
against corrosion in nuclear fuel reprocessing plants. This work aimed at investigating this possibility. TiO2
films were deposited on AISI 304 stainless steel substrates by metal-organic chemical vapor deposition
(MOCVD). The corrosion behavior of the coated specimens was assessed in nitric acid solution at different
temperatures using electrochemical impedance spectroscopy and potentiodynamic polarization curves. The
presence of metallic ions in the testing solutions was assessed using neutron activation analysis (NAA). The
results showed that the corrosion resistance of the stainless steel substrate was significantly improved by the
TiO2 films. Film porosity was considered as a major aspect of the deposition process as it strongly influenced
the overall corrosion resistance of the coated specimens. Chemical analysis of the testing solution by NAA
pointed that the total amount of released metallic ions was effectively reduced by the TiO2 films.
REFERENCES
1) H. Hu, X. Liu, C. Ding, J. Alloys Compd. 498 (2010) 172.
2) B. Raj, U. K. Mudali, Prog. Nucl. Energ. 48 (2006) 283.
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FEASIBILITY OF NIOBIUM OXIDE-BASED FILMS TO PREVENT CORROSION OF
AISI 304 STAINLESS STEEL IN NUCLEAR FUEL REPROCESSING PLANTS
Olandir Vercino Correa1, Mara Cristina L. de Oliveira2, Renato Altobelli Antunes3, Mitiko
Saiki1, Oswaldo Pereira Vilela da Silva Junior4, Marina Fuser Pillis1
Nuclear and Energy Research Institute, IPEN-CNEN/SP, Materials Science and Technology Center, 2Electrocell Ind. Com.
Equip. Elétricos LTDA., 3Federal University of ABC (UFABC), 4Prest Vácuo Ltda., São Paulo, Brazil, [email protected]
1
The integrity of metallic materials is a major concern in nuclear fuel reprocessing plants due to the possible
leakage of radioactivity is the component fails. Surface degradation by corrosion processes is regarded
as a relevant failure mechanism in this environment. Typically, nitric acid is employed as the processing
medium in nuclear fuel reprocessing plants. Thus, metallic materials should withstand surface degradation
in contact with nitric acid solution at different concentrations and temperatures. Protective coatings are the
technological approach to improve the surface properties of austenitic stainless steels components used
in nuclear reprocessing plants. Niobium oxide-based films has been reported to enhance the corrosion
properties of austenitic stainless steel substrates in near-neutral and sulfuric acid-based acidic solutions1,2.
However, the effectiveness of these films to protect austenitic stainless steels in typical nuclear reprocessing
plants environments is not addressed in the literature. In this context, the aim of this work was to investigate
the influence of Nb2O5 films on the corrosion properties of AISI 304 stainless steel substrates in nitric
acid solutions. The corrosion resistance was evaluated using electrochemical impedance spectroscopy (EIS)
and potentiodynamic polarization tests. The presence of metallic ions in the testing solutions was assessed
using neutron activation analysis (NAA). The corrosion morphology was observed using scanning electron
microscopy (SEM). The results indicated that the presence of Nb2O5 films effectively improved the corrosion
resistance of the stainless steel substrate by reducing the corrosion current density and increasing charge
transfer resistance. The amount of Fe, Ni and Cr ions released to the testing solution significantly decreased
for the coated-specimens as determined by NAA. Nb2O5 films can be considered promising candidates to
protect stainless steel components against corrosion in nuclear fuel reprocessing plants.
REFERENCES
1) G. Ramírez, S.E. Rodil, H. Arzate, S. Muhl, J. J. Olaya, Appl. Surf. Sci. 257 (2011) 2555.
2) C.-H. Liang, C.-H. Cao, N.-B. Huang, Int. J. Min. Met. Mat. 19 (2012) 328.
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Instrumental Neutron Activation Analysis of Bidens pilosa, a
medicinal plant used for diabetes treating.
Rodolfo Daniel Moreno Reis Gonçalves1, Paulo S. Cardoso da SILVA1
Instituto de Pesquisas Energéticas e Nucleares IPEN - CNEN/SP, São Paulo, Brazil, [email protected]
1
Medicinal plants have been used since long time ago in traditional medicine for treatment of several
diseases. Bidens pilosa, popularly known as picão-preto in Brazil, is a plant commonly found in several
regions of the world, among its many applications in folk medicine, stands out its use for the treatment of
Diabetes Mellitus. The objective of this study was to evaluate the elementary concentration of Mg, Mn and
V in samples of B. pilosa and its growth substrate, since their minerals may influence the pharmacological
activity of plants, and diabetes patients studies have indicated that some minerals also exert influence in its
metabolism. Obtaining samples has done by planting seeds. Three months after planting, the adult plants
were collected and separated into a two groups: the control group and another called treatment group,
in which solution containing Mg, Mn and V elements were added. Soil was collected from the beds of
plants and also separated into control and treatment. To evaluate the concentration of minerals Instrumental
Neutron Activation Analysis technique was used. Samples were irradiated in the nuclear reactor IEA-R1
under a neutron flux of 1012 n cm-2 s-1 for 20 seconds and then counted in hyperpure germanium detector.
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Radioanalytical Chemistry
4th-INCC 2014 I 4th International Nuclear Chemistry Congress
Study of potassium content in Mexican Nopal (opuntia ficus indica), by
nuclear methodology using the Gamma Spectrometry
Guillermo Espinosa1, Jose-Ignacio Golzarri1, Edgar Padilla-Soriano2, Juan Manuel
Navarrete Tejero3, Trinidad Martínez Castillo3
Instituto de Física, Universidad Nacional Autónoma de México. Circuito de la Investigación Científica, 2Facultad de Química,
Universidad Nacional Autónoma de México. Ciudad Universitaria, 3Facultad de Química, Universidad Nacional Autónoma de
México. Edificio D, Ciudad Universitaria, Mexico, Mexico, [email protected]
1
Mexico is one of the largest producers of nopal (opuntia ficus indica). This “vegetable” is consumed on a
daily basis by the Mexican population, being a source of food nutrients. Among its benefits is considered
the content of potassium, which is essential for human life and health. So the study and characterize of the
contents of these elements in the nopal, based on their biological species and place of cultivation is very
important from the point of view of population health, food, agriculture and trade.
In this study, was analyzed the content of potassium of the Mexican cactus (opuntia ficus indica) grown in
5 different regions in the Mexican Basin, where the 67% of the nopal is produced, for human consumption.
The used methodology is by gamma spectrometry with hyperpure germanium detector (HPGe) and
multichannel analyzer (MCA) with Maestro® software.
The results show interesting aspects on the concentration of potassium in the nopal; this concentration will
depend primarily: a) of the geological characteristics of the location where the nopal was grown; b) that
potassium concentrations may vary substantially from a region to another, with the same species of nopal as
a reference; and c) that this concentration may also vary from one growing season to another.
This information can be very valuable for the development of the nopal production as potassium natural
source on the human health.
This work was partially supported by UNAM-DGAPA-PAPIIT Project IN103013.
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ARSENIC SPECIES IN FRESH-WATER AND MARINE FISH LIPIDS BY CHEMICAL
SEPARATION AND NEUTRON ACTIVATION
Youqing Shi1-2, Amares CHATT1
Trace Analysis Research Centre, Department of Chemistry, Dalhousie University, 2Atomic Energu of Canada Limited, Halifax,
Canadá, [email protected]
1
It is well known that seafood contains relatively high levels of arsenic and that the toxicity of arsenic is
dependent on its chemical form. The extraction of arsenic compounds from seafood samples is an important
step towards its speciation analysis. Past studies mostly concentrated on the identification of water-soluble
arsenic species, which of course, accounts for much of the arsenic in marine organisms. Although methanolwater mixtures and methanol-water-chloroform mixed solvents were employed by many researchers to
extract arsenic species from similar organisms, a methanol-MIBK-water system was used in this work to
study the lipid-soluble arsenic species by NAA.
The MIBK phase contained most of the lipid-soluble arsenic which was determined by instrumental neutron
activation analysis (INAA) in Canadian seafood samples. Several INAA methods using both fission spectrum
and epithermal neutrons in conjunction with conventional and anticoincidence gamma-ray spectrometry
were developed. Since the MIBK phase contained very little sodium and low levels of arsenic, it was decided
to apply an INAA method consisting of 20-30 min irradiation at a fission neutron flux of 5x1011 cm-2 s-1 at
the Dalhousie University SLOWPOKE-2 reactor facility followed by 7-10 d decay and 3-5 h counting. The
detection limit was less than 10 μg kg-1. The method was validated by analyzing several reference materials
from NIST and NRC.
The levels of lipid-soluble arsenic in marine and fresh-water fish samples were found to be low (~ 0.17 mg kg-1)
followed by canned marine fish (~ 0.5 mg kg-1). The Dogfish Liver reference material (NRC DOLT-2) had the
highest level of lipid-soluble arsenic (3.6 mg kg-1).
A correlation analysis between the lipid content as the mass percentage of seafood (dry mass basis) and the
lipid-soluble arsenic content as the mass percentage of the total arsenic gave a correlation coefficient of 0.76.
Although more data points are needed to establish a more definite relationship between the concentrations of
lipid and the lipid-soluble arsenic, the results obtained in this work clearly indicate that the higher the lipid
content the higher is the lipid-soluble arsenic in the seafood.
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Determination of uranium traces in nuclear reactor IEA-R1 pool
water
Adonis Marcelo SALIBA-SILVA1, Eneas Tavares de Oliveira1, Olair dos Santos1, Michelangelo
Durazzo1
Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), São Paulo, Brazil, [email protected]
1
Uranium traces in nuclear reactor pools are normally inspected avoiding levels over 50 μg.L-1. The environment
protection control for uranium content establishes the uranium level being less than 15 μg.L-1 in order to
discard wastewater as sewage. There is a toughing of government regulation in this field, since this level was
officially 30 μg.L-1 up to recently. The environmental policies imposes not only strict standards of control,
but also, higher frequency of sampling and well settled statistics industrial control, using instruments as
SPC (Statistical Process Control). Nuclear Fuel Plant of IPEN is working on an adequate control system
based on uranium traces evaluation throughout the wastewater originating in its fuel fabrication, mainly in
the chemical manipulation of UF6 and UF4 sector. As a similar work, we can provide the level of uranium
content for operational routine of IEA-R1 nuclear reactor pool water. There are several routes to determine
the uranium content in tap water, using the polarography, already known in the literature. In the present study,
the chosen chemical determination of uranium traces uses the electrochemical method ACSV (adsorptive
cathodic stripping voltammetry). This method should account with strict setting of variables in order to
achieve feasible error level. The main route uses chloranilic acid [CA] (2,5-dichloro-3,6-dihydroxy-1,4benzoquinone) which is not straightforward in use. Depending on the uranium content level, the response
of redox reaction of the UO22+ imposes many restrictions and varies intensively with reduction potential
of [UO2(CA)2]-complex. The main considered variables are the analyzed sample volume, the pH of the
solution, the acidulation acid and additions to improve the peak response, as EDTA-2Na and KNO3. As nontrivial determination, the U-traces determination demands intense research to establish a proper method. In
this work, we present the results of IEA-R1 reactor water determination, after operation routine. The results
show uranium content level of 100% less than 10 μg.L-1), within 6% error, which represents good results for
small quantities and equipment limitation. In general, we are scrutinizing the uranium content in IEA-R1
pool water to keep it below 30 μg.L-1. This inspection is fully crucial, since the level for the future RMB
reactor is still unknown and should be as less as possible, once the power of the reactor will be of 30 MW.
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CESIUM ACCUMULATION IN PLANTS FROM BRAZILIAN BIODIVERSITY
HOTSPOTS
Elvis Joacir de FRANÇA1, Elisabete A. De Nadai Fernandes2, Marcia Valéria de Fátima da
Encarnação Sá Miranda1, Rebeca da Silva Cantinha1
Divisão de Pesquisa e Desenvolvimento, Centro Regional de Ciências Nucleares do Nordeste, Comissão Nacional de Energia
Nuclear, 2Radioisotopes Laboratory, Centro de Energia Nuclear na Agricultura, Universidade de São Paulo, São Paulo, Brazil,
[email protected]
1
No essentiality of cesium is observed for any organism, however, this chemical element is quite present
in ecosystems mainly due to this chemical similarity to the nutrient potassium. Moreover, its radioactive
isotope,137Cs, is one of the most relevant environmental contaminants associated to nuclear energy. In this
research, cesium was determined by instrumental neutron activation analysis – INAA in the most abundant
plants from Cerrado and Atlantic Forest. All conservation units of the Biota Project “Diversity, dynamic and
conservation of forests from the São Paulo State: 40 ha of permanent parcels” were studied for the presence
of Cs in tree leaves. Leaf samples were oven-dried at 60 oC, milled until size of particles of 0.5 mm and
irradiated in a thermal neutron flux of 1013 cm-2 s-1 at the Nuclear Research Reactor IEA-R1, Instituto de
Pesquisas Energéticas e Nucleares. Quantu software was employed to calculate Cs mass fractions and its
analytical expanded uncertainties at the 95% confidence level. Results showed that Vochysia tucanorum,
Myrsine umbellata, Bathysa meridionalis, Coussarea contracta, Rudgea jasminoides, Alsophila sternbergii
and Schefflera angustissima were the most accumulator species. Vochysia tucanorum accumulated the
highest amount of cesium, which was about 650 times compared to the minimum observed value of 0.011
mg kg-1. Consequently, this Cerrado tree species was considered to be hyper-accumulator of cesium.
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Activity levels of gamma-emitters and barium concentrations in
Brazil nuts
Maria José A. ARMELIN1, Vera Akiko MAIHARA1, Silvia Maria Franciscato Cozzolino2, Paulo
S. Cardoso da SILVA1, Mitiko Saiki1
Instituto de Pesquisas Energéticas e Nucleares (IPEN / CNEN – SP), 2Faculdade de Ciências Farmacêuticas, Universidade de São
Paulo (USP), São Paulo, Brazil, [email protected]
1
In recent years, nutritionists have suggested daily intake of a certain portion of Brazil nuts (Bertholletia
excelsa, family Lecythidaceae) because of its high selenium concentration. In addition to selenium, it is
known that barium and radium are also accumulated in Brazil nuts. Smith1 also reported that the Brazil
nut tree has a unique capacity for accumulating barium and radium in its fruit. This accumulation for Ba
and Ra has been explained as a possible formation of organic complexes which increase the mobility of
alkaline earth ions, particularly for these two elements, favoring their movement redistribution during fruit
development. In addition, the soil of the Amazon region where the Brazil nuts grow on wild trees, is rich in
the mineral Hollandite (Ba2Mn8O16)2.
Barium is not considered essential and can be toxic depending on its chemical form. The Ba2+ ion and
the soluble compounds of barium (notably chloride, sulfide, nitrate, hydroxide) are toxic to animals and
humans. Several radioactive substances are considered carcinogens (Group 1 agents), according to the
IARC publication3. The carcinogenic activity is attributed to radiation, for example radiation emitted by Ra
radionuclides (224Ra, 226Ra and 228Ra) and their decay products. In this study, the activity concentrations of:
natural (226Ra, 228Ra, and 40K) and artificial (137Cs) radionuclides were evaluated by gamma ray spectrometry,
and Ba concentration were determined by Instrumental Neutron Activation Analysis (INAA) in samples of
Brazil nuts acquired in several points of sale between 2010 and 2013. The activity concentrations for the
investigated samples ranged from: (0-26), (113–379), (20–80) and (17–317) Bq kg-1 for 137Cs, 40K, 226Ra and
228
Ra, respectively. Taking into account, the highest activity concentration obtained for each radionuclide
and, assuming an annual consumption of 1.5 kg, the estimated annual effective dose due to ingestion of
Brazil nuts is 27% of annual dose limit of 1 mSv y-1 to the public exposure, according to ICRP4. Preliminary
results for the Ba concentration showed a variation from 32.7 to 60.3 µg g-1.
REFERENCES
1) K. A. Smith, Plant and Soil 34 (1971) 369.
2) J. C. Chang, W. H. Gutenmann, C. M. Reid, D. J. Lisk, Chemosphere 30-4 (1995) 801.
3) International Agency for Research on Cancer – IARC. Available in: http://www.iarc.fr/. Accessed on 30/01/2014.
4) ICRP, Protection of the public in situations of prolonged radiation exposure. ICRP Publication 82. Oxford: Pergamon Press
(1999).
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A study on elemental composition of tree barks for using in
atmospheric pollution monitoring
Eliane Conceição dos Santos1-2, Mitiko Saiki1
Instituto de Pesquisas Energéticas e Nucleares, IPEN-CNEN/SP, 2Instituto de Química, Universidade de São Paulo, São Paulo,
Brazil, [email protected]
1
The accumulation of atmospheric aerosols on tree barks has been widely studied as a tool for the identification
of pollution sources¹ because bark analyses allow the monitoring of extensive geographical areas with easy
and low cost of sampling. Since the elemental composition in barks depends on several parameters, the
objective of this study was to compare elemental concentrations found in samples collected in tree trunks of
different diameters, in opposite sides of a tree trunk and of distinct arboreal species, Tipuana (Tipuana tipu)
and Sibipiruna (Caesalpinia peltophoroides). Bark samples were collected at a height of 1.5 m from the soil
and were cleaned using a nylon tooth brush. For analysis, about 2 mm of the bark surface layer was removed
using a Ti grater and it was ground in an agate mortar. The bark elemental composition was determined by
Neutron Activation Analysis (NAA). Aliquots of samples and standards of elements irradiated with neutrons
at the IEA-R1 nuclear research reactor were analyzed by gamma ray spectrometry. The quality control of
the analytical results evaluated by analyzing INCT Virginia Tobacco Leaves certified reference material
(CRM) presented values of |z-score| ≤ 2, indicating that the procedure of NAA applied is suitable for the
analyses. The comparison between the results showed increase of elemental accumulation with the trunk
diameter or age of the tree for barks collected in heavy vehicular traffic area. However, for samples from low
vehicular traffic area there was the decrease of concentrations indicating possible elemental leaching with
the time. The barks collected in opposite sides of the tree trunk presented different elemental concentrations.
Elemental concentrations in tree barks varied depending on the tree species, some elements in Tipuana
species showed higher concentrations than those obtained for Sibipiruna probably due to the difference in
bark porosity. As conclusion, parameters evaluated in this study must be considered in collecting tree bark
samples for biomonitoring studies.
REFERENCES
1) F. Guéguen, P. Stille, M. Millet, Chemosphere. 85 (2011) 195.
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Assessment of Fountain Water Quality of Towns of the Iron
Quadrangle, Brazil
Cláudia Alves Ferreira1, Helena Eugênia Leonhardt Palmieri1, Maria Ângela de B. C.
MENEZES1
Centro de Desenvolvimento da Tecnologia Nuclear/Comissão Nacional de Energia Nuclear, CDTN/CNEN, Belo Horizonte,
Brazil, [email protected]
1
The Iron Quadrangle, with an area of approximately 7200 km2, is worldwide known for its diversity. It is
located in the mid-south of the state Minas Gerais, between the basins of the Velhas river (sub-basin of the
San Francisco river) and of the Piracicaba river (sub-basin of the Doce river). The public supply of the water
is done mainly by impound of water of water sheds and, in many places, the population uses spring water
and, mainly, fountains. Even today, this water is used by both the local population and visitors who trust
its quality. However, the popular idea that natural fountain water is clean, is misleading since many toxic
elements may be naturally present. In order to estimate the overall water quality, a total of 34 fountain water
samples were collected from 18 towns in this region. The concentration results of the rare earth elements,
uranium, trace elements determined by ICPMS and the physiochemical parameters, besides gross alpha and
gross beta activities in these fountains, were evaluated. This study highlights the water quality evaluation
destined in consumption human.
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The influence of sample properties and sample geometry on the
accuracy of the gamma-ray spectrometry.
Eliane C. dos Santos1-2, Rodrigo K. Kawassaki1-2, Thais S.P. Neto1-3, Frederico Antonio
Genezini1, Mitiko Saiki1
Instituto de Pesquisas Energéticas e Nucleares- IPEN-CNEN/SP, 2Instituto de Química, Universidade de São Paulo, 3Faculdades
Oswaldo Cruz, São Paulo, Brazil, [email protected]
1
The comparative method of Neutron Activation Analysis (NAA) has been widely applied to analyze several
kinds of samples and, in order to avoid analytical errors, the sample and elemental standard must be identical
or comparable in its dimensions and matrix composition. In order to improve analytical results, in this
study the variations in counting rates due to the influence of sample property (density), sample geometry
(dimensions), effect of dead-time and pile-up and the difference of the sample holder were investigated. These
influences were studied using two simulated samples of 241Am and 152Eu which were prepared by pipetting
these radioactive tracers on sheets of filter paper. The gamma ray measurements were carried out using a
Digital Spectrum Analyzer coupled to a hyperpure Ge detector and the gamma spectra were processed using
Genie 2000 software. The gamma ray energies, in keV, of each tracer utilized were the following: 241Am
(59.54) and 152Eu (121.78, 344.29, 778.92, 964.11, and 1408.0). The absorption of gamma radiation was
studied for the samples presenting different densities such as plant, lichen, brain tissue, filter paper, mineral
supplement, shale, soil and metallic iron. Results obtained indicated the decrease of counting rates with the
increase sample dimensions. As expected, this effect was more pronounced when the counting position was
closer to the detector. The dead-time and pile-up effects led to a change in the counting efficiency and the
results indicated that dead time has to be limited to 7.9% in order to avoid substantial errors. As expected the
counting rates decreased with the density of sample due to gamma ray absorption and the effect was greater
at low gamma energy. The simulated samples measured using nine sample holders presented counting rates
ranging from 1.3% to 5.2%, depending on the gamma ray energy measured. From the results obtained one
may conclude that sample geometry and sample properties should be considered to ensure a consistent high
quality of the analysis and adequate conditions for gamma ray spectrometry were proposed in this study.
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4th-INCC 2014 I 4th International Nuclear Chemistry Congress
MAJOR ELEMENTAL FEATURES OF A PORTUGUESE BREAD-WHEAT ARCHIVAL
COLLECTION, DETERMINED BY INSTRUMENTAL NEUTRON ACTIVATION
ANALYSIS
Catarina Isabel Alves Lourenço Galinha1-2-4, Adriano M. G. Pacheco2, Maria do Carmo
Freitas1, Ana R. P. Costa3, Nuno M. B. Pinheiro3, Benvindo Maçãs3, Ana Sofia Almeida3,
Hubert T. Wolterbeek4
URSN/CTN-IST, University of Lisbon, 2CERENA-IST, University of Lisbon, 3INIAV, National Institute of Agricultural and
Veterinary Research, Savavém, 4Department of Radiation Science and Technology, Faculty of Applied Sciences, Delft University
of Technology, Portugal, [email protected]
1
More than just being one of the “big three” cereal crops (with maize and rice altogether), wheat is the staple
food of humankind, with a history that is closely entwined with humanity’s own. Despite ongoing arguments
on core areas and/or time scales, agricultural beginnings in the Old World are invariably traced back to cereal
domestication, i.e. einkorn and emmer wheats (and barley), foremost among the seven Pre-Pottery Neolithic
founder food crops. Opportunistic gathering and incipient cultivation may have preceded domestication for
quite a long time, with the modern, free-threshing forms of tetraploid durum wheat (Triticum durum) and
hexaploid bread wheat (Triticum aestivum) eventually appearing some 8500 years before present. The status
of wheat as the universal cereal of ancient agriculture has been kept through this day. Tonnage (though not
acreage) of wheat grown worldwide may have been overtaken by both maize’s and rice’s shortly before the
turn of last century; however, wheat remains unrivalled as to overall area and latitudinal range of cultivation,
nutritional relevance, and civilisational significance at large. Current production is split between an
overwhelming majority of hexaploid bread wheat (about 95 %), and a remaining share of (mostly) tetraploid
durum wheat plus small amounts of hulled-grain wheat species (einkorn, emmer, spelt).
Given such a background, no wonder that wheat germplasm was among the first to be stored in archival
collections and seed banks around the world, despite early technical difficulties in preserving genetic
resources as germplasm holdings. Following the first morphological and taxonomic inventory of Portuguese
wheats, a collection of cultivars has been maintained, replanted and documented by the National Institute
of Agricultural and Veterinary Research (INIAV-Elvas). This work addresses the current status of major
elemental nutrients and contaminants in a pool of 51 accessions of bread wheat in the INIAV-Elvas collection.
All grain samples were irradiated at the Portuguese Research Reactor (RPI; CTN-IST, Sacavém) for 5 h, at
a thermal-neutron fluence rate of 2.25x1012 cm-2 s-1, together with comparator disks of an Al-0.1%Au alloy.
Gamma spectra were acquired with a liquid N2-cooled, high-purity Ge detector. Elemental concentrations
were determined through k0-standardized, instrumental neutron activation analysis (k0-INAA), and quality
control was carried out by concurrent analysis of NIST-SRM®1567a, NIST-SRM®1568a and INCT®OBTL-5. In the discussion, focus is given to essential nutrients like Fe, Mg, Se and Zn, and also to historical
trace contaminants like As, as compared to current ionomic traits in modern European wheats. Special
attention is paid to the levels of Se, for which wheat acts as an important source in human diets, with a
view to curbing its deficiency in Portuguese cultivars through long-term (plant breeding) or short-term
(agronomic biofortification) improvement strategies.
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Radiation Chemistry
4th-INCC 2014 I 4th International Nuclear Chemistry Congress
IMPROVEMENT IN THE RADIATION STABILITY OF EPDM/INCORPORATED
EPDM POWDER/CARBON BLACK COMPOUND
Ludmila de Ysasa Pozzo Kiyan1, Traian Zaharescu2, Duclerc Fernandes Parra1, Ademar
Benévolo Lugão1
IPEN, Center of Chemistry and Environment, 2INCDIE ICPE CA, Department of Advanced Materials, São Paulo, Brazil,
[email protected]
1
The recovery of polymer wastes is a promising task, which can be done by the application of radiation
processing on proper compositions. Even though radiation has a scission effect on macromolecules, the
presence of a certain monomer leads to more stable systems. The most convenient procedure for polymer
recycling is crosslinking under irradiation, when new intermolecular bridges promote stability.
The incorporation of EPDM powder and carbon black in the matrix of block polymer makes possible to
reuse this elastomer for economical purposes.
This paper analyzes the possibility of stability improvement by the addition of acrylic acid in EPDM systems.
The start materials are EPDM containing 30 and 50 phr of EPDM powder loaded with 40 phr off carbon
black. After electron beam irradiation these materials gain a certain stability, which was characterized by
nonisothermal chemiluminescence. The involvement of radicals in the modification of oxidability after
EB exposure is revealed by the increase of activation energy as the dose enhanced by their contribution to
material strengthening. The difference between the two compositions consists of the feed of free radicals
from the higher content of EPDM powder.
The two stages of irradiation bring about two different effects. The first EB processing creates a relative
stability of processed EPDM compounds, while g-irradiation performed in the presence of crosslinking
monomer (acrylic acid, at the load of 3 phr) improves the degree of gelation.
The resistance against oxidation is improved after the g-treatment of composed samples because acrylic acid
participates at the formation of new intermolecular bridges and the diffused oxygen amount is diminished.
The presence of 0.3 phr of antioxidant (Irganox 1010) restricts the decay of radicals by their reaction with
oxygen.
The Charlesby-Pinner representation reveals the similar behavior of radiation crosslinked samples, but the
p/q ratios are 1.72 and 1.78 for EPDM containing 30 phr and 50 phr, respectively of EPDM powder. The
analytical relationships which depict the gel accumulation are:
for 30 phr: S+S1/2 = 1.72 (1/D) + 8.59
for 50 phr: S+S1/2 = 1.78 (1/D) + 6.39
The oxidative degradation advances differently in two samples containing 30 and 50 phr powder, due the
higher.
This study is a start investigation of polymer recovery using radiochemical processing, which confirms the
application of nuclear energy in material conversion.
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
SIMULTANEOUS USE OF ANION EXCHANGER AND SR RESIN FOR EFFICIENT
STRONTIUM ISOLATION FROM COMPLEX MATRICES
Gorana Karanović1, Ivana Milanović1, Željko GRAHEK1
Ruđer Bošković Institute, Zagreb, Croácia, [email protected]
1
Among all radionuclides which are released into the nature one of the most studied is 90Sr. Reason is that
radioactive strontium isotopes are highly radiotoxic fission products (especially 90Sr with long half-life),
and as such they are an interesting subject for various investigations, from their distribution and behavior
in natural systems, to their influence on human health. As a rule, a determination of radioactive strontium is
complicated and time-consuming, especially if isotope 89Sr is present in the sample.
The determination requires isolation of small amounts of strontium from complex matrices, its separation
from large quantities of calcium (and other elements), and the detection of radioactive isotopes on the
available instruments. The most difficult step is separation of Sr from Ca due to their similarities in chemical
behavior. For this purpose, in a standard procedure, a method of precipitation with fuming nitric acid is
used. Due to its aggressiveness, this method can be replaced with a method of chromatographic separation
on a specific Sr resin. The Sr resin enables highly efficient separation of Sr from Ca and other elements.
Therefore, the resin is increasingly used in the analysis of radioactive strontium in different kinds of
samples. In practice, it is found that the efficiency of strontium isolation depends on the concentration of
Ca, K, Na, and other present elements. It decreases with the increase of their concentration above certain
limits. If efficiency of isolation (recovery) is reduced, the detection limit (MDA) will increase. In the case
of low level activity determination, it will significantly expand uncertainty of determination. The decrease
of recovery can be prevented by increasing the amount of the Sr resin used for isolation. However, the Sr
resin may lose capacity during usage so desired effect can be lost. Sr can also be separated from Ca and a
number of elements on anion exchange column using alcoholic solution of nitric acid. Unlike the Sr resin,
anion exchanger does not lose capacity hence it can compensate disadvantages of the Sr resin. Therefore,
the main aim of this work is developement of a robust and efficient method of strontium isolation from
different types of samples. It involves simultaneous use of both resins. Also, the impact of the most abundant
element concentrations in natural samples on the efficiency of strontium isolation will be examined. Special
attention will be given to the separation of Rb from Sr and other elements in combination of both resins. Rb
has several radioactive isotopes that could interfere with the determination of 89,90Sr and should be separated
prior detection. On the other hand, their mutual separation is important in isotope dating analysis.
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4th-INCC 2014 I 4th International Nuclear Chemistry Congress
EVALUATION OF PHYSICO-CHEMICAL PROPERTIES AND BIODEGRADATION
OF POLYMERIC MEMBRANES BASED CHITOSANA, STARCH, AND
POLYVINYLPYRROLIDONE (PVP) SYNTHESIZED BY GAMMA RADIATION AT
DIFFERENT DOSES AND DOSE RATES
Jorge Gabriel dos Santos Batista1, Ana Carolina Moreira Fonseca2, Ademar Benévolo Lugão3
Instituto de Pesquisas Energéticas e Nucleares (IPEN / CNEN - SP), São Paulo, Brazil, [email protected]
1
The use of gamma radiation in the synthesis process of products for human use has increased in recent years.
This fact is due to the advantages of the process, which in the case of polymers is part of the synthesis and
physical crosslinking agent process that can sterilize the product, already in its final packaging, increasing the
agility of the process by reducing two steps into one. In this study, it was evaluated the influence of the dose
rate of gamma radiation, in relation to the physico-chemical characteristics of the synthesized membranes
based on natural polymers (chitosan and starch) and the synthetic polymer (polyvinylpyrrolidone), in
different proportions. According to the dose rate and the total dose, an increased fragility of the membranes
composed of polysaccharides occurs. The opposite occurs with the PVP at a certain dose, when its strength
rises due to the increase of the crosslinking degree. The polymers were subjected to doses ranging from 1
to 100 kGy and two different dose rates. The results demonstrated that it is possible to change the rate of
biodegradation of polymeric membranes and change their physicochemical properties using different doses
of gamma radiation at different dose rates1,2.
REFERENCES
1) Muzzarelli, R. A. A.; Jeuniaux, C.; Gooday, G. W. Chitin in Nature and Technology, Plenum Press, New York, 1986.
2) Wasikiewicz, J.M. et al., Degradation of chitosan and sodium alginate by gamma radiation, sonochemical and ultraviolet
methods. Radiation Physics and Chemistry, vol. 73, Issue 5, August 2005, pages 287-295
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
EFFECT OF γ-IRRADIATION ON RADICAL SCAVENGING, REDUCING POWER
AND LIPID PEROXIDATION INHIBITION PROPERTIES OF HYDROALCOHOLIC
EXTRACTS FROM MALVA NEGLECTA
José Virgílio Santulhão Pinela1-2, Amilcar L. Antonio1-3, Lillian Bouçada de Barros1, Ana M.
Carvalho1, M. Beatriz P. P. Oliveira2, Isabel C. F. R. Ferreira1
Centro de Investigação de Montanha (CIMO), ESA, Instituto Politécnico de Bragança, 2REQUIMTE/Departamento de Ciências
Químicas, Faculdade de Farmácia, Universidade do Porto, 3Centro de Ciências e Tecnologias Nucleares, IST, Universidade de
Lisboa, Bragança, Portugal, [email protected]
1
Radiation processing technology has been used to improve food security, safety and quality. However there
are a few reports in the literature on the effect of irradiation on bioactivity of herbs and medicinal plants1.
Hence, the present work was undertaken to investigate the dose-response effects of gamma irradiation on
free radical scavenging, reducing power and lipid peroxidation inhibition properties of hydroalcoholic
extracts prepared from wild Malva neglecta Wallr. In the north-eastern of Portugal, this annual herbaceous
plant is traditionally eaten raw as leafy vegetable or prepared in herbal beverages due to its disinfectant and
anti-inflammatory properties2. Thus, dried M. neglecta samples were exposed to 0 (control), 1, 5 and 10
kGy of γ-rays in a 60Co experimental chamber. After irradiation, processed samples were extracted using
methanol:water (80:20 v/v) and the radicals scavenging activity evaluated through the 2,2-diphenyl-1picrylhydrazyl (DPPH) free radicals assay, the reducing power by the ferricyanide/Prussian blue assay,
and the lipid peroxidation inhibition by β-carotene/linoleate and thiobarbituric acid reactive substances
(TBARS) assays. The obtained results suggest that the different irradiation doses affect the extracts
bioactivity. In general, the free radicals scavenging activity and the reduction power decreased in irradiated
samples (except for 5 kGy in the DPPH assay) compared with the non-irradiated control. On the other hand,
the lipid peroxidation inhibition was improved by the irradiation treatment (except for 1 kGy in the TBARS
assay). Both β-carotene/linoleate and TBARS assays showed low EC50 values (corresponding to a high lipid
peroxidation inhibition), while the DPPH assay demonstrated the highest ones (corresponding to a low free
radicals scavenging effect). The results herein reported support the use of gamma-irradiation as an effective
technology to maintain or improve the lipid peroxidation inhibition properties of hydroalcoholic extracts of
M. neglecta, and their traditional use in folk medicine.
Acknowledgments: FCT (Portugal) for financial support to the research centre CIMO (PEst-OE/AGR/
UI0690/2011), J. Pinela (SFRH/BD/92994/2013) grant and L. Barros contract.
REFERENCES
1) N. S. Rajurkar, K. N. Gaikwad, M. S. Razavi, Int. J. Pharm. Pharm. Sci. 4 (2012) 93-96.
2) A. M. Carvalho, Biblioteca de Ciências nº 35 (2010).
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4th-INCC 2014 I 4th International Nuclear Chemistry Congress
Analysis of phenolic compounds in Tropaeolum majus L. processed by
ionizing radiation
Amanda Cristina Ramos Koike1-2, João C. M. Barreira2, Lillian Barros2, Celestino SantosBuelga3, Anna Lucia C. H. Villavicencio1, Isabel C. F. R. Ferreira2
Instituto de Pesquisas Energéticas e Nucleares (IPEN - CNEN/SP), 2Centro de Investigação de Montanha (CIMO), ESA, Instituto
Politécnico de Bragança, 3Grupo de Investigación en Polifenoles (GIP-USAL), Faculty of Pharmacy, University of Salamanca,
São Paulo, Brazil, [email protected]
1
Tropaeolum majus L. (garden nasturtium) is an ornamental plant that belongs to Tropaeolaceae family, native
to South America in the Andes and that is widely distributed around the world. Its flowers are extensively
used in food preparations and have strong spicy flavours as watercress, being also acknowledged for their
antioxidant properties and high content of phenolic compounds [1, 2]. The use of edible flowers as food
ingredients requires new approaches to improve conservation and safety. The extension of post-harvest
storage, preserving the quality of the plants, will benefit the industrial development [3]. Food irradiation
is a method that can be used for the extension of shelf life of perishable commodities and to increase food
safety [4]. The purpose of this study was to evaluate the dose-response effects of gamma and electron
beam irradiation (doses of 0, 0.5, 0.8 and 1 kGy) on the phenolic profile of garden nasturtium, using
HPLC-DAD-ESI/MS. Kaempferol-O-hexoside-O-hexoside was the most abundant compound
in all the studied samples (8 and 14 mg/g of extract, after gamma and electron beam irradiation,
respectively), followed by 5-O-caffeoylquinic acid (2.3 mg/g for both irradiation technologies) and
3-O-caffeoylquinic acid (2.2 and 2.0 mg/g for gamma and electron beam irradiation, respectively).
Regarding anthocyanins, pelargonidin-3-O-sophoroside and delphinidin-O-dihexoside were the most
abundant compounds (4 and 2 μg/g, respectively, after both types of irradiation). According to the obtained
results, the applied irradiation treatments seemed feasible technologies to keep the phenolic composition
and preserve the quality of edible flower petals and might be useful to expand the post-harvest storage,
preserving the quality of T. majus.
Acknowledgments: FCT- Portugal for financial support to CIMO (strategic project PEst-OE/AGR/
UI0690/2011), João C.M. Barreira (SFRH/BPD/72802/2010 grant) and L. Barros (“Compromisso para
a Ciência 2008” contract). The GIP-USAL is financially supported by the Spanish Government through
the Consolider-Ingenio 2010 Programme (FUN-C-FOOD, CSD2007-00063). This research is included in
a Bilateral action FCT-CNPq, Portugal/Brazil 2014 and CNEN, CAPES, CNPq and IPEN-CNEN/SP for
financial support to Amanda Koike.
REFERENCES
1) Creasy, R. The Edible Flowers Garden. Periplus Editions, Boston (1999).
2) Garzón, G.A. and Wrolstad R.E. Food Chemistry, 114, (2009) 44-49.
3) Rop, O., Mlcek, J., Jurikova, T., Neugebauerova, J., Vabkova, J. Molecules, 17, (2012). 6672-6683.
4) Farkas, J. Trends in Food Science and Technology, 17, (2006) 148-152.
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
Impact of gamma irradiation on chemical composition of Melissa
officinalis L.
Eliana Pereira1-2, Amanda Cristina Ramos Koike3, Amilcar L. Antonio1-4, Lillian Barros1,
Isabel C. F. R. Ferreira1
Mountain Research Centre (CIMO), ESA, Polytechnic Institute of Bragança, 2GIP-USAL, Faculty of Pharmacy, University of
Salamanca, 3Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), 4Centro de Ciências e Tecnologias Nucleares, IST,
Universidade de Lisboa, São Paulo, Brazil, [email protected]
1
Food irradiation is increasingly recognized as an effective decontamination technique that ensures the
chemical and organoleptic quality of the product. This decontamination method leads to a reduction in
the application of chemical fumigants and preservatives, which are currently used by the food industry in
order to provide higher safety for the consumer since it does not leave chemical residues in food. Melissa
officinalis L. (commonly known as lemon balm) is used in several countries as aromatic, medicinal herb
and also for culinary use. Traditionally it is consumed in infusions for various disorders such as headaches,
gastrointestinal disorders (flatulence cramps, spasms and indigestion), nausea, nervousness, anemia, vertigo,
syncope, malaise, asthma, bronchitis, amenorrhea, heart failure, arrhythmia, insomnia, epilepsy, depression,
psychosis, hysteria, ulcers and wounds; it is also used as anti-bacterial [1-3]. The aim of the present work
was to evaluate the effects of different doses of gamma irradiation (0 kGy – control, 1 kGy and 10 kGy) on
nutritional value and chemical composition of M. officinalis. The nutritional value was determined according
to official analysis procedures. The composition in free sugars, fatty acids and tocopherols was determined
by high performance liquid chromatography-refraction index detection (HPLC-RI), gas chromatographyflame ionization detection (GC-FID), and HPLC-fluorescence, respectively. According to the results
obtained this decontamination process has not modified the concentration of fructose and glucose; the dose
of 1 kGy protected the concentration of α- and γ-tocopherol, sucrose, and macronutrients, with exception of
carbohydrates. In general, 10 kGy protected sucrose, threalose, oxalic, quinic and malic acids, and γ- and
δ- tocopherols level. Overall, irradiation might represent a suitable solution for M. officinalis postharvest
treatment, since the doses of 1 and 10 kGy preserved various chemical compounds and the nutritional of the
studied plant.
Keywords: Melissa officinalis L.; food irradiation; chemical composition
Acknowledgments: The authors are grateful to Fundação para a Ciência e a Tecnologia (FCT, Portugal) for
financial support to CIMO (strategic project PEst-OE/AGR/UI0690/2011). The authors are also grateful to
“MaisErvas - Aromáticas e Medicinais” for samples providing.
REFERENCES
1) K. Dastmalchi, H.J. Damien Dorman, P.P. Oinonen, Y. Darwis, I. Laakso, R. Hiltunen, LWT 41 (2008) 391-400.
2) C. Weitzel, M. Petersen, Phytochem. 72 (2011) 572-578.
3) H.B. Owczarczyka, W. Migdal, B. Kędzia, Radiat. Phys. Chem. 57 (2000) 331-335.
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INFLUENCE OF ANTIOXIDANT LOADING ON THE γ-EXPOSURE OF ETHYLENEPROPYLENE TERPOLYMER
Heloísa Augusto Zen1, Traian Zaharescu2, Mariana Mădălina Marinescu2, Sandra Regina
scagliusi1, Elizabeth Carvalho Leite Cardoso1, Ademar Benevolo Lugão1
IPEN, Center of Chemistry and Environment, 2INCDIE ICPE CA, Department of Advanced Materials, São Paulo, Brazil,
[email protected]
1
The long term applications of polymers require the improvement in material native resistance upon oxidation.
One of the most convenient procedures for the achievement of high chemical strength is the addition of
antioxidants. The material performances are directly related with the ability of antioxidant for to scavenge
of hydrocarbon radicals formed during radiolysis.
The use of ethylene-propylene elastomers in nuclear energy applications is possible due to the protection
activity of some additives. In this work EPDM rubber was loaded with different antioxidants at the
concentration of 0.5 phr, these additives act as chain breakers by replacing hydroxyl proton with radiolytic
radicals.
Samples of polymer under different states of modification were prepared by addition of appropriate amount
of stabilizer into EPDM chloroform solution. Films of 40 mm were obtained by removal of solvent. Gamma
exposure was accomplished in an irradiator provided with 137Cs source at room temperature. Dose rate was
0.4 kGy h-1. A large dose range was covered up to 500 kGy for the illustration of advanced stabilization
effect exhibited by several antioxidants during a nuclear event.
The radiochemical yields, G, of the main oxygenated molecular configurations appeared during radiation
oxidation were calculated for the evaluation of stabilization contributions of the tested antioxidants. The
efficiency in radiochemical stability was evaluated by chemiluminescence measurements of oxidation
induction times (isothermal determinations) and onset oxidation times (nonisothermal determinations).
FTIR spectroscopy was applied for characterizing the modification in oxidation states along γ-irradiation.
The discussion on the stabilization efficiency related to the chemical structure of used additives is presented.
This study is complementary of other previous investigations, when the spectral evolution during polyolefin
degradation under γ-irradiation was investigated1-3.
REFERENCES
1)T. Zaharescu, M. Giurginca, S. Jipa, Polym. Degrad. Stab. 63 (1999) 245.
2)Z. Kačarević-Popović, D. Kostoski, L. Movacović, N. Miljević, B. Šećerov, J. Serb. Chem. Soc. 69 (2004) 1029.
3)M. Gardette, A. Perthue, J-L. Gardette, T. Janecska, E. Földers, B. Pukánsky, S. Therias, Polym. Degrad. Stab. 98 (2013)
2383.
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THERMAL RESISTANCE OF EPDM/IIR SYSTEMS UNDER γ-IRRADIATION
Sandra Regina Scagliusi1, Traian Zaharescu2, Heloísa Augusto Zen1, Elizabeth Leite
Carvalho Cardoso1, Silviu JIPA3, Ademar Benévolo Lugão1
IPEN, Center of Chemistry and Environment, 2INCDIE ICPE CA, Department of Advanced Materials, 3University of Valachia,
Faculty of Science and Arts, São Paulo, Brazil, [email protected]
1
The application areas of butyl rubber concern the tire production in automotive industry, gaskets and
membranes for chemical engineering, commodities and toys destined to daily life. The blending of IIR
rubbers with various elastomers brings about useful alternatives to neat materials.The evaluation of the
degradation behavior allows the selection of proper systems, which are the most resistant to accelerated
ageing.
Three IIR loadings (5, 10 and 20 phr) of EPDM were brought into consideration for different butyl rubber
structures: pristine, chlorinated and brominated IIR. For advanced degradation γ-irradiation was applied
at dose rate of 0.4 kGy.h-1 over a large dose range (up to 300 kGy). The stability investigations by FTIR
and chemiluminescence (isothermal and nonisothermal procedures) were accomplished on thin films
(thicknesses 100 µm).
The presence of halogenated IIR influences the thermal and radiation stabilities of there compounded
systems1. The sequence in oxidation resistance reveals the influence of halogen atoms, because of their
different electronegativity: EPDM-IIR neat > EPDM-IIR Br > EPDM-IIR Cl > EPDM neat.
The exposure of EPDM/IIR samples to γ-irradiation induces progressive oxidative degradation. The evolution
of calculated carbonyl and hydroxyl indexes depicts the unlike behavior in respect with the scission process.
The most stable is EPDM/neat IIR blend, which has the lowest sensitivity on radiochemical degradation.
The present work demonstrates the negative influence of halogen substitution on the radiation stability,
when modified IIR is processed. The most important feature of EPDM/neat IIR is the higher radiochemical
strength, which recommends it as a suitable resistant material. However, the compounding of ethylenepropylene terpolymer with butyl rubber can be considered as a product with improved stability against
oxidative ageing.
REFERENCES
1)T. Zaharescu, M. Giurginca, S. Jipa, Polym. Degrad. Stab. 63 (1999) 245.
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RN-222 AND STABLE ISOTOPES AS A NATURAL TRACER IN GROUNDWATERSURFACE WATER INTERACTIONS AT THE ARTIFICIAL RECHARGE SYSTEM
Yoon Yeol Yoon1, Kil Yong Lee1, Soo Young Cho1, Kyu Chul Ha1
Geologic Environment Division, Korea Institute of Geoscience and Mineral Resources (KIGAM), Daejeon, South Corea,
[email protected]
1
Environmental isotopes have become a routine component of hydrogeology, complementing geochemistry
and physical hydrogeology in groundwater resource and groundwater contamination studies. And
geochemical tracers may be used to determine groundwater/surface water interaction. Environmental
radionuclides such as C-14, H-3, Rn-222 and stable isotopes have been used to understand groundwater/
surface water interaction. The different geochemical tracers have potential advantages and disadvantages.
Stable isotope ratios are relatively easy to measure and are often measured as part of general water quality
studies. However, if groundwater and surface water have overlapping δ18O and δD values, these tracers
may not be easy to use, and seasonal variation variability of the isotopic composition of the evaporation
flux can not be measured directly and theoretical approaches are charged with high uncertainty. Radon is
an important tracer that has increased in usage over the past two decades as the ease of measurement has
improved. The properties of 222Rn(half-life 3.8 days, chemically inert) and high activities in groundwater
make it a powerful and potentially useful tracer of hydrological processes at the interface between surface
and sub-surface water bodies.
Radon and stable isotopes were used as a tracer of groundwater/surface water interaction study of groundwater
recharge system near Nakdong river in Korea. Artificial recharge system was consisted of four input, six
monitoring and one pumping well. For recharge groundwater, river water was injected through four input
well. To understand groundwater recharge by river water injection, Rn-222 and stable isotope samples were
collected at six monitoring well during recharge operation time.
For one day recharge operation period, Rn-222 concentration was decreased at the observation well
groundwater. During the experiment Rn-222 activity variation of each monitoring wells were 170-300
pCi/L at OBS-1, 100-180 pCi/L at OBS-2, 830-1510 pCi/L at OBS-3, 160-690 pCi/L at OBS-4, 590-930
pCi/L at OBS-5 and 120-230 pCi/L at OBS-6. OBS-1 and 5 were decrease about 35 % due to surface water
dilution effect but OBS-6 was increased due to surround groundwater input effect. The stable isotopes
were similar trend with radon concentration but OBS-4 sample was different with other samples. This
means different groundwater was entered during recharge operation time. To understand surface watergroundwater interaction, 14 days artificial recharge experiment was performed and groundwater collected
during the operation time. This long-term experiment result showed radon concentration variation was small
at the OBS-1 and 2. However, OBS-3 was increased and OBS-4 was decreased with time.
REFERENCES
1) Ian Cartwright, Harald Hofmann, Melissa A. Sirianos, Tamie R. Weaver, Craig T. Simmons, J. Hydrol. 405 (2011) 333.
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THE CONTRIBUTION OF MINING ACTIVITIES ON ANTHROPOGENIC INPUT OF
Cu, Pb AND Zn IN THE CANANÉIA-IGUAPE SYSTEM
Keila Modesto Tramonte1, Paulo Alves de Lima Ferreira1, Andreza Portella Ribeiro1-2,
Rubens César Lopes Figueira1, Michel Michaelovitch de Mahiques1
Instituto Oceanográfico da Universidade de São Paulo, 2Universidade Nove de Julho (UNINOVE), Mestrado de Gestão Ambiental
e Sustentabilidade, São Paulo, Brazil, [email protected]
1
The Cananéia-Iguape System suffered important environmental changes due to the opening of Valo Grande
Channel, which connect this system to the Ribeira de Iguape River. The mining activities in the Ribeira
Valley between 1945 and 1995 affected the river basin, reaching this system through Valo Grande. The aim
of this study was to recognize the contribution of mining activities to the enrichment of Cu, Pb, and Zn in
Cananéia-Iguape system, using data from geochemistry and geochronology of sediment cores collected
along this system. In this study, 30 sediment samples taken from the upper layer (0-50 cm) of 5 cores were
subjected to sequential extraction of metals based on the BCR procedure.1 The method establishes fractions
that extract exchangeable metals and associated with carbonates, Fe and Mn oxides, organic matter and
sulfides. The mechanisms of association of these metals show that they were incorporated anthropically in
sediments and, therefore, have greater potential for mobility. The quantification of elements was performed
using ICP-OES technique.
The ages of the samples were estimated from the sedimentation rates of the cores (CAN 02, 04, 05 and 072 and
CAN 10 determined by the Laboratory of Inorganic Chemistry of Oceanographic Institute of the University
of São Paulo). The technique was 210Pb gamma spectrometry, using a low background Ge detector.3 The
period of deposition of the samples ranged between 1926 and 2008. The maximum available content was
18.74 mg kg-1 for Cu, 177.55 mg kg-1 for Pb and 123.03 mg kg-1 for Zn. For Cu and Zn was observed that
in all samples, except one for the Zn, the available content is lower than the reference value estimated for
these elements in the region, 30.2 and 90.1 mg kg-1, respectively. However for Pb, in approximately 83% of
the samples the available content was higher than the value reference this element (20.6 mg kg-1). Although
the Cu content in the samples remains low, it was observed a increase in their concentration in 1953; the
maximum available content of Cu was determined in 1993. It also observed a peak in Zn concentration
in 1953. The Pb concentration during the period of mineral exploration showed high available content in
most samples, almost always higher than its reference value. However, an increase in the concentration was
observed in 1953 (maximum available content), 1958, 1970, and 1993. From these results, it was possible
to recognize the anthropogenic input of Pb in cores and the contribution of mining activities, considered as
the only source of this metal in the region.
REFERENCES
1) Pueyo, M., Rauret, G., Lück, D., Yli-Halla, M., Muntau, H., quevauviller, Ph., López-Sánchez, F.J. J. Environ. Monit. 3
(2001) 243.
2) Mahiques, M. M.; Figueira, R.C.L.; Salaroli, A.B.; Alves, D.P.V.; Gonçalves, C. Environ Earth Sci. 68 (2013) 1073.
3) Figueira, R.C.L., Tessler, M.G.; Mahiques, M.M.; Fukumoto, M.M. Soil Found. 47 (2007) 649.
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SEDIMENTATION PROCESSES IN THE SEMI-ENCLOSED BAY DEDUCED FROM
VERTICAL PROFILES OF 137Cs MASSIC ACTIVITIES (KAŠTELA BAY, ADRIATIC
SEA, CROATIA)
Ivanka Lovrenčić Mikelic1, Višnja OREŠČANIN2, Krunoslav ŠKARO3, Delko BARIŠIĆ1
Laboratory for Radioecology, Division for Marine and Environmental Research, Ruđer Bošković Institute, 2Advanced Energy
Ltd, 3Hydrographic Institute of the Republic of Croatia, Oceanographic Department, Zagreb, Croacia, [email protected]
1
This study gives the systematic insight into sedimentation processes in the Kaštela Bay as a whole system
instead of at the isolated individual sampling stations. Its results are equally applicable to other aquatic
environments with comparable processes and sedimentation environments. Vertical depth profiles of 137Cs
massic activities were used to: i) Study sedimentation processes; ii) Distinguish sedimentation conditions in
different parts of the Bay; iii) Partly determine the pathways of the terrigeneous sedimentary material input
into the Bay. It was found that the continuous, undisturbed sedimentation, with only occasional sedimentation
anomalies, takes place in the central and south parts of the Bay, while the sedimentation conditions in
the west part of the Bay are more complicated. West part of the Bay is characterized by the extremely
slow sedimentation of the coarse grained sediment or even by the erosion and selective resuspension of
the fine grained particles followed by the resedimentation in other parts of the Bay as the predominating
processes. It was also observed that the upper 10 cm of the Kaštela Bay sediment are the most exposed to
homogenization. East part of the Bay is strongly influenced by the Jadro River and anthropogenic activities,
which is reflected in higher 137Cs massic activities, strong sediment mixing, and increased sediment input.
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STATISCAL ANALISYS OF DISCREPANTS RADIOECOLOGICAL DATA USING
MONTE CARLO BOOTSTRAP METHOD
Arykerne Nascimento Casado da Silva1, Romilton dos Santos Amaral1, José Wilson Vieira1,
José Araújo dos Santos Júnior1
Nuclear Energy Department of Federal University of Pernambuco, Recife, Brazil, [email protected]
1
Researchers have been made using the bootstrap resampling method since 1979. There are operational
difficulties in obtaining samples in radioecological studies, doing the researcher sometimes work with
an insufficient number of data. Moreover, it is often the appearance of outliers in the sample data. As
a consequence, the statistical analysis of samples may require the use of complex parametric analytical
methods. The bootstrap method is performed using the high data processing capability of today’s computers.
So-called samples are obtained by Monte Carlo method through a random process of the actual data provided,
considering that they are independent and uniformly distributed. The present work was developed aiming
to apply the bootstrap method in statistical analysis of radioecological data and to assist the researcher in
obtaining the most appropriate estimators for the population parameters. The method uses the R software,
a powerful interactive tool for statistical calculations. The tool also allows object-oriented programming
through interpretation. The data used were 14 samples of 226Ra in forage palm (Opuntia spp.) and they showed
a range concentration from 1,495 to 25,000 mBq.kg-1 in dry matter, with simple arithmetic average 5,965.86
± 5,903.05 mBq.kg-1. The bootstrap resampling procedure with 1,000 iterations through the developed
algorithm obtained an average value of 6,013.61 ± 1,597.83 mBq.kg-1. This value is more representative of
the whole sample average, because it was not influenced by the outliers. It was possible to conclude then that
the bootstrap method has valid application for univariate statistical analysis of radioecological data
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A 10-year record of seasonal variation of 7Be in particulate matter
and plants of Cerrado biome, Brazil
Bruno Burini Robles Arine1, Marco Antonio Proença Vieira Moraes1, André Luis Lima de
Araújo1
Centro Tecnológico da Marinha em São Paulo - Laboratório Radioecológico, Sorocaba, Brazil, [email protected]
1
Be is a cosmogenic radionuclide produced through the process of spallation of nitrogen and oxygen in
the upper atmosphere by high energy particles from cosmic rays. 7Be has a half-life of nearly 53 days and
its concentration in the atmosphere is 1-7 mBq.m-3, which may vary according to several factors, such as
solar cycles, latitude, atmospheric convergence zones and seasonality. This radionuclide can be carried by
tropospheric aerosols which deposit on land surface by either dry or wet deposition. Annual deposition of
7
Be in soil appears to be, however, highly dependent on rain cycles. This paper presents the history of 10
years of 7Be concentration around Aramar Experimental Centre in Iperó region (Brazil), predominantly
a Cerrado biome. In addition, responsible factors were investigated for the change in environmental 7Be
concentration through atmospheric particulate samples and vegetation, collected since 2003 and analyzed by
gamma spectrometry technique. The observed results show a negative correlation between 7Be concentration
in airborne particulate matter and rainfall volume during the sampling period (r² = -0.7). Moreover, a
positive correlation between concentration of 7Be in vegetation and net precipitation was observed (r² = 0.9).
Environmental factors such as average temperature, atmospheric pressure, wind speed and direction, as well
as flux of cosmic rays and solar activity, did not correlate with 7Be concentration in either airborne particles
or vegetation (p > 0.05). Therefore, it is suggested that rainfall plays the largest role in environmental 7Be
concentration.
7
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Determination of Cesium Contamination in Marine Sediments from
North of Gulf of Mexico
Miguel Angel Zúñiga Pérez1, Juan Manuel Navarrete Tejero1, Trinidad Martínez Castillo1,
Samuel Tejeda Vega2
Facultad de Química, Edificio D, Universidad Nacional Autónoma de México, 2Instituto Nacional de Investigaciones Nucleares,
Gerencia de Ciencias Ambientales, D.F. México, Mexico, [email protected]
1
The cesium contamination was investigated for seven marine sediment samples taken up from North of
Gulf of Mexico at different depths (50 – 2500 m). This contamination was determined by measuring various
parameters such as cation exchange capacity (CEC), partition coefficient (KD) and the previously proposed
radiation contamination factor (RCF)1,2,3, which is defined as the ratio of activity concentrations (Bq/kg)
between cesium-137 and potassium-40. This research shows the low affinity of cesium with the marine
sediment samples comparing with earlier studies (CEC = 12.21 – 20.62 meq/100 g; KD = 0.045 – 0.054 L/
kg); in the same way, shows the very low activity due to cesium-137 (artificial radioisotope and fission product
of uranium) if compared with potassium-40 (natural radioisotope, primordial) (%RCF = 0.58 – 1.21 %).
REFERENCES
1) M. Navarrete, J. Golzarri, G. Espinosa, G. Müller, M. A. Zúñiga, M. Camacho, Applications in Physical Sciences, InTech,
(2011) 225-246.
2) J. M. Navarrete, G. Müller, J. I. Golzarri, G. Espinosa, Int. J. Environ. Health, 5 (2011) 318-323.
3) J. M. Navarrete, M. A. Zúñiga, G. Espinosa, J. I. Golzarri, J. Chem. Chem. Ing. 6 (2012) 1010-1015.
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Microbial effect on the aqueous uranium(VI) adsorption by
bentonite under anaerobic condition
Seung Yeop Lee1, Ji Young Lee1, Min Hoon Baik1, Jong Tae Jeong1, Kyungsu S. Kim1
Korea Atomic Energy Research Institute (KAERI), Daejeon, South Corea, [email protected]
1
The understanding of the interaction between radionuclides and the near-field materials is very important for
assessing the safety of the repository site. There have been recent reports that indigenous sulfate-reducing
bacteria (SRB) are present in commercial bentonite.1,2 We, thus, tried to find out the microbial effect on the
uranium(VI) adsorption by local granite and bentonite. The adsorption features of U(VI) by the near-field
rock and minerals are important determinants of the mobility of U species in the HLW repository site.
In our experiment, two solid phases, granite and bentonite, were reacted with aqueous solutions of U(VI)
in the addition of H2 or/and SRB at neutral pH and anaerobic condition (Fig. 1). The aqueous U(VI)
concentration (5×10-5 M) in a serum bottle gradually decreased to a certain level following the interaction
between U(VI) and the adsorbents. The U(VI) adsorption onto granite was greater as the added SRB is
gradually activated with time. The reason seems that the hexavalent uranium(VI) was biologically reduced
to tetravalent uranium(IV) or a portion of U(VI) would be adsorbed onto the suspending SRB. This shows
that SRB can be an important agent to the U(VI) adsorption.
Fig. 1. The decrease patterns of aqueous uranium(VI) concentration by (a) granite and (b) bentonite, which
were significantly affected by the added SRB or/and hydrogen gas.
However, the U(VI) amount adsorbed by bentonite was slightly larger in the presence of H2 gas regardless
of the SRB addition. This means that there was a slight difference of U adsorption between ‘bentonite
alone’ and ‘bentonite + H2 gas’ conditions. In a condition of H2 addition, the adsorbed U(VI) quantity by the
bentonite increased more than 5~8% compared to that of H2 absence. The difference of the U(VI) adsorption
capacity between the two conditions may be attributed to the naturally surviving SRB in the bentonite, where
SRB can be more activated by the provision of H2. Therefore, the bentonite that has indigenous SRB seems
to more effective in the adsorption of U(VI), if H2 gas is diffused into it and plays a role of electron donor
for the U(VI) reduction. This result could imply that if U(VI) is reacted with the bentonite in a repository,
U(VI) migration would be retarded somewhat by the SRB surviving in the compacted bentonite buffer.
REFERENCES
1) P. Masurat, S. Eriksson, K. Pedersen, Appl. Clay Sci. 47 (2010) 51.
2) J. Y. Lee, S. Y. Lee, M. H. Baik, J. T. Jeong, J. Korean Radioact. Waste Soc. 11 (2013) 95.
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Radiological characterization of the varieties Burley and
Virginia of Nicotiana tabacum L. cultivated in Brazil
Carolina Fernanda da Silva1, Sandra Regina Damatto1, Rique Jones Ferreira Xavier da Rocha1,
Marcos Medrado de Alencar1
Instituto de Pesquisas Energéticas e Nucleares (IPEN / CNEN - SP), São Paulo, Brazil, [email protected]
1
Brazil is the largest exporter and second largest producer of tobacco worldwide, according to the production
of the crop year 2009/2010. The tobacco plant (Nicotiana tabacum L.) is used to manufacture all derivatives
and the chemical composition of the resulting tobacco varies with the type of tobacco leaves, how they are
grown, the region where they are cultivated, the characteristics of preparation (compression, filter and paper)
and the temperature variations resulting from the incomplete combustion of tobacco. Tobacco products are
extensively used throughout the world and the most consumed are cigarettes, cigars and narghile. The
damaging effects that these products cause to human health are discussed worldwide, and many researches
are performed with the aim of relating the use of these products with various illnesses. There is a lack of
information about the radiological characterization of the tobacco plant both in international and Brazilian
literature. This paper presents the preliminary results of 238U, 234U, 230Th, 232Th, 226Ra, 228Ra, 210Pb and 210Po
concentration in the varieties Burley and Virginia of Nicotiana tabacum L., which are the most cultivated
in Brazil. Plants from these varieties were cultivated in pots with organic substrate and fertilizer and
also acquired from the producers and analyzed by alpha spectrometry for U and Th isotopes and 210Po
determination, and gross alpha and beta counting, 228Ra, 226Ra and 210Pb determination. The whole plant,
from both places, was analyzed; root, steam, leaves, as well as the organic substrate, the fertilizers and
the soil. The results obtained presented higher values for 210Pb in leaves when compared with the other
parts of the plant, probably due to its atmospheric deposition; these results obtained for 210Pb were also
compared with results from the international literature, and they showed that the Brazilian tobacco has
higher values, but they are in agreement with a previous work that analyzed 210Pb in Brazilian cigarette.
The preliminary results obtained in this paper can contribute with a better knowledge and understanding of
these radionuclides behavior found in Nicotiana tabacum L., cultivated in Brazil, since Brazil is the largest
exporter of tobacco in the world.
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SEDIMENTATION RATES BY 210Pb METHOD AND TRACE ELEMENTS BY INAA IN
TWO SEDIMENT CORES FROM THE TIETÊ RIVER, SÃO PAULO, BRAZIL
Sandra Regina Damatto1, Flavio R. Rocha2, Daiane Baumgardt1, Lucas M. Castro2,
Bruno Tappiz2, Paulo S. Cardoso da SILVA2, Deborah I. T. FÁVARO2
Laboratório de Radiometria Ambiental - IPEN-CNEN-SP, 2 Laboratório de Análise por Ativação com Nêutrons, Centro do Reator
de Pesquisas (LAN/CRPq) - IPEN/CNEN-SP, São Paulo, Brazil, [email protected]
1
The Tietê River, with 1,100 km of extension, is one of the most economically relevant rivers of the State
of São Paulo. It is also considered one of the most polluted rivers in the world, especially when it passes
through the metropolitan region of São Paulo (RMSP). As a result of pollution observed since the 1950s,
a project was established with the aim of evaluating the historic concentration of some metal and trace
elements in sediment cores dated by 210Pb method. The cores were sampled in several points of the river,
from its source in Salesópolis up to its mouth, in the Paraná River. This study presents the results obtained
in two sediment cores collected in Santana de Parnaiba and Salto de Itú, both cities located after the RMSP.
Instrumental neutron activation analysis was used to determine As, Ba, Br, Ca, Ce, Co, Cr, Cs, Eu, Fe, Hf,
La, Lu, Na, Nd, Rb, Sb, Sc, Sm, Ta, Tb, Th, U, Yb and Zn elements. Precision and accuracy were checked
by means of certified reference materials BEN (Basalt-IWG-GIT), SL-1 (Lake Sediment – IAEA) and
Soil-5 (IAEA), that shows certified concentration values for all elements analyzed. The INAA results were
compared to the NASC reference values (North American Shale Composite) and regional basal values. The
enrichment factor (EF) and geoaccumulation index (GI) were used to assess the presence of anthropogenic
pollution sources. The sedimentation rates were obtained by the 210Pb method and presented values which
show that these reservoirs are affected by the rainy season and urban expansion of its surroundings.
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RADIOTRACERS SORPTION STUDIES TO EVALUATE THE METAL REMOVAL
POTENTIAL OF METAL-RESISTANT BACTERIAL BIOFILM
Katia Noriko Suzuki1, Melissa Nogueira Sondermann1, Fatima P. Canesin1, Mirian Araujo
Carlos Crapez2, Elisamara Sabadini-Santos1, Luis F Bellido3, Edimar C. Machado4,
Wilson Machado1, Ricardo Tadeu Lopes5, Alfredo Victor Bernedo Bellido1
Departamento de Geoquímica, Universidade Federal Fluminense (UFF), 2Programa de Pós-Graduação em Biologia Marinha,
Universidade Federal Fluminense (UFF), 3Instituto de Radioproteção e Dosimetria (IRD/CNEN), 4Instituto Federal de Educação,
Ciência e Tecnologia do Rio de Janeiro, 5Laboratório de Instrumentação Nuclear, Universidade Federal do Rio de Janeiro, Niterói,
RJ, Brazil, [email protected]
1
Natural bacterial biofilm can retain trace metal contaminants within the sediment-water interface from
aquatic systems. Methodologies that integrate the evaluation of physical, chemical and biological processes
are requested to investigate the biofilm potential to be used in bioremediation efforts1,2. The objective of this
work was to evaluate the removal of metals by artificial bacterial biofilms with induced resistance to metals.
For the initial sorption study an adaptation of the constant suspension method3 was used to determine the
distribution coefficients of the radiotracers (65Zn and 51Cr) between the dissolved phase (unfiltered seawater)
and the bacterial biofilm. A known number of bacteria (1.13x109 cells/cm3) with amplified Zn resistance
(prepared in the Laboratory of Bacterial Ecology – UFF), was inoculated into 100 mL of unfiltered seawater.
The mixture was constantly stirred by a shaker and known amounts of radiotracers were added to the solution
and shaken for 24 hours at room temperature. At predetermined time intervals samples of the mixture
were filtered (Millipore filter of 0.22 µm pore size) and the radiotracer activities of the filter and filtrate
were analyzed by γ-counting, using a high-purity germanium detector (HPGe). The preliminary results
showed that chromium removal varied from 0% to 6% for samples without metal-resistant biofilm and 0%
to 10% for samples with metal-resistant biofilm. Zinc removal varied from 0% to 19% for samples without
metal-resistant biofilm and 0% to 22% for samples with metal-resistant biofilm. These low differences were
attributed to the low bacterial biomass used during the experiment, making it difficult to assess the potential
sorption of radioisotopes by bacterial biofilms. On the other hand, the sorption for 65Zn was approximately
one order of magnitude higher than observed for 51Cr(VI), which was expected because of the use of bacterial
biofilm with amplified Zn resistance in this microcosm experiment. Current experiments are using higher
bacterial biomass to elucidate the extent in which metal-resistant biofilm can affect the radiotracer sorption.
REFERENCES
1) A. Serra, N. Corcoll, H. Guash, Chemosphere. 74 (2009) 633.
2) A. M. Farag, D. A. Nimick, B. A. Kimball, S. E. Church, D. D. Harper, W. G. Brumbaugh, Archives of Environmental
Contamination and Toxicology. 52 (2007) 397.
3) E. K. Duursma, C. J. Bosch. Neth. J. Sea Res. 4 (1970) 395.
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Radiosensitizer effect of selenium in cells challenged with
gamma radiation (60Cobalt)
Bárbara Abranches de Araujo Porto1, Luciana Mara Costa Moreira1, Frederico Haddad
Ribeiro1, Luiz Cláudio Moura Belo1, Maria José Neves1
Lab. Radiobiologia, CDTN/CNEN, Belo Horizonte, Brazil, [email protected]
1
Radiotherapy is one of the most common therapies against cancer. Co-60 irradiators (cobalt-60 linear
accelerators) are used to treat malignant tumors routinely in hospitals around the world. Exposure to ionizing
radiation can induce changes in cellular macromolecules and generate reactive oxygen species, which damage
all organelles and cell components producing oxidative damage that culminate in oxidative stress. Oxidative
stress is a situation in which the balance between oxidants and antioxidants is broken resulting in excessive
production of free radicals species that overcome the antioxidant capacity. Selenium is a micronutrient
considered as antioxidant, anti-inflammatory, which could prevent cancer. Selenium in biological systems
exists as selenoproteins. In human 25 selenoproteins have been identified, some of them are antioxidant
enzyme as glutathione peroxidase. The yeast Saccharomyces cerevisiae, unlike mammalian cells is devoid
of selenoproteins and proliferates through the fermentation, the microbial equivalent of aerobic glycolysis
in mammals, a biochemical pathway used by cancers cells. Cancer cells use the metabolic reprogramation
to face the harsh conditions find inside the organism. Several reports show pro-oxidant effects of selenium
compounds at lower doses in human malignant cells and the same it not observed in normal cells. Then,
selenium opens a great therapeutic potential in cancer treatment. Our objective was to determine the role
of selenium when cells are challenged with ionizing radiation in a 60Co gamma irradiator. The oxidative
damage to cell and cell death were determined after selenium treatment and gamma irradiation. Our results
showed that selenium has a radio sensitizing function playing an oxidant role in cells.
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Evaluation of anticancer activity of lanthanide gadolinium and
its radioisotope 159Gd against malignant glioblastoma
Izabela Galvão1, Raquel Gouvea dos Santos1, Maria José Neves1
Lab. Radiobiologia, CDTN/CNEN, Belo Horizonte, Brazil, [email protected]
1
There is an urgent need for multifactorial strategy to improve the prognosis of cancer, especially glioma.
New antitumor drugs based on metal complexes have been investigated as an important class of potent
therapeutic agents against cancer. Actually different complex of gadolinium (motexafin, gadodiamide) and
Gd neutron capture therapy have been investigated as alternative antitumoral treatment. An increase of
anticancer potency has been observed by concomitant combination of irradiation and chemotherapeutic
agents. Beta emitting radionuclides can deliver high radiation dose rate on tumor site. 159Gd is a radionuclide
that presents this characteristic, but studies showing its cytotoxic activity and mechanism of action against
tumors are still limited. The purpose of this work was to investigate Gd and 159Gd as antitumor agents and
the involvement of reactive oxygen species in the induction of gadolinium cytotoxicity. Gadolinium was
cytotoxic for glioblastoma cells in a dose dependent manner. It produced nuclear changes, free radicals and
alteration of redox balance. Gadolinium effect was more accentuated in the Zn/Cu superoxide dismutase
(sod1) deficient cells. The treatment with 159Gd, (IC50 =0.34 - 0.33 ± 0.001 mM), proved to be more
potent than Gd, (IC50 = 2.07-1.61 ± 0.001 mM). The presence of the radioactivity improved the gadolinium
performance and a dose around 45 pSv was very efficient. All these findings led us to conclude that
gadolinium may be a metal of choice for developing new drugs for cancer treatment.
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THEORETICAL STUDY OF Re AND Tc DMSA COMPLEXES
Alejandro BLANCO-GONZÁLEZ1, Daniel HERNÁNDEZ-VALDÉS1, Zalua RODRÍGUEZ-RIERA1,
Ulises Jaúregui-Haza1, Luis DUCAT-PAGES2, Luis PIZARRO-LOU2
Instituto Superior de Tecnologías y Ciencias Aplicadas (InSTEC), 2Centro de Isótopos, La Habana, Cuba, [email protected]
1
Meso-2,3-dimercaptosuccinic acid (DMSA) is used in nuclear medicine as ligand for the preparation of
radiopharmaceuticals for diagnostic and therapy. DMSA has been the subject of numerous investigations
during the past three decades and lots of new and significant information of the chemistry and pharmacology
of DMSA complexes have emerged. In comparison to other ligands the structure of many DMSA complexes
is unclear up today. The structures and applications of DMSA complexes are strictly dependent on the
chemical conditions of their preparation, especially pH and the ratio of components. A computational study
of M-DMSA (M = Tc, Re) complexes has been performed using density functional theory. Different isomers
for M(V) and M(III) complexes were study. The pH influence over ligand structure was taken into account
and the solvent effect was evaluated using an implicit solvation model. The fully optimized complex of
[ReO(DMSA)]2- syn-endo-isomer shows a geometry similar to the X-ray data. NMR theoretic calculations
were performed for Tc and Re complexes as well as DMSA ligand and the results were compared with the
literature. The correlation of these results with the available experimental data on these systems allows
bringing some understanding of the chemistry of DMSA complexes.
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BIODISTRIBUTION OF 4,4’-DIFORMYL-1,6-DIPHENOXYHEXANE LABELED WITH
IODINE-131
Nesibe Avcibasi1, Hande Efe1, Hasan Demiroğlu2, Gökçen Topal3, Uğur Avcıbaşı2
Ege University - Ege Higher Vocational School, 2Celal Bayar University - Faculty of Arts and Science, Department of Chemistry,
Celal Bayar University, Faculty of Medicine, Department of Nuclear Medicine, İzmir, Turkey, [email protected]
1
3
Monomeric and dimeric anti-cancer drug aldehyde conjugate compounds have a highly promising
application platform to improve therapeutic effectiveness and safety profiles in the treatment of multiple
types of cancers1-3.
The aim of the current study is to synthesize a novel aldehyde conjugate compound, 4,4́-diformyl1,6-diphenoxyhexane, (DFPH) also, to radiolabel related this compound with 131I and to investigate
radiopharmaceutical potential of radiolabeled compound on healthy experimental animals.
To achieve this, DFPH given in the Figure 1 was synthesized in the first stage. In the next stage, this
compound was radiolabeled with 131I then quality-control studies were done using radiochromatographic
method. Radiolabeling yield was found to be about 95%.
In the last, scintigraphy and biodistribution studies were done. Static image of DFPH was given in the
Figure 2. It was observed that radiolabeled compound showed high uptake in the uterus, the ovarian and the
breast after the biodistribution studies and results were agreed
with that of scintigraphy studies.
In conclution, the novel aldehyde compound was successfully synthesized and radiolabeled with 131I using
iodogen method for the first time. Showing high uptake of compound in the uterus, the ovarian and the
breast reveals the potential of this radioiodinated compound to be used in the diagnostics and therapy in
diseases related with these organs. Using 4,4́-diformyl-1,6-diphenoxyhexane for this purpose will be able to
be possible, if the cell and the xenograft studies planned to be carry out in subsequent stages give positive
results.
REFERENCES
1)E. Acton, G. Tong, G, J. Med. Chem. 24(6) (1981) 669.
2)B. R. ]. Abdella, J. A. Fisher, Envir Health Perspect. 64 (1985) 3.
3)S. L. Blair, Cancer Res. 57 (1997) 152.
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INVESTIGATION OF THERAPEUTIC EFFICIENCY OF PHENYTOIN (PHT)
LABELED WITH RADIOACTIVE 131I IN THE CANCER CELL LINES
Cansu Uzaras1, Uğur Avcıbaşı1, Emin İlker Medine2, Ayfer Yurt Kilçar2, Zümrüt Biber
Müftüler2, Hasan Demiroğlu1, Perihan Ünak2
Celal Bayar University, Faculty of Arts and Science, Department of Chemistry, 2Ege University, Institute of Nuclear Sciences,
Department of Nuclear Applications, Manisa, Turkey, [email protected]
1
PHT given in Figure 1 is an antiepileptic drug. It is useful to treat partial seizures and generalized tonicclonic seizures but not primary generalized seizures such as absence seizures or myoclonic seizures. PHT is
believed to protect against seizures by causing voltage-dependent block of voltage-gated sodium channels.1
Phenytoin has low affinity for resting sodium channels at hyperpolarized membrane potentials.2
The aim of this study is to determine the incorporations of Phenytoin radiolabeled with 131I (131I-PHT)
on U-87 MG, Daoy and A549 cancerous cell lines. In the first stage, cold labeling study with 127I of PHT
was carried out by using HPLC method. Secondly, radiolabeling and quality-control studies of PHT were
carried out by using thin layer radiochromatography. In this context, it was found that the binding yield was
obtained to be about 95% for radiolabeled PHT (131I-PHT). Subsequently, cell culture studies were carried
out and binding yields of 131I, 131I-PHT on U-87 MG, Daoy and A549 cancerous cells were investigated,
respectively. In addition to these studies, the optimum time, the optimum concentration and the specific
activity parameters of PHT were determined. Finally, cytotoxicities of PHT were inspected and apoptosis
studies of PHT were carried out on same cancer cells given above by Tunnel method.
In conclusion, 131I-PHT was investigated in the cell culture studies for the first time. 131I-PHT was obtained
in high radiochemical purity and high yield by direct electrophilic iodination of PHT. 131I-PHT was shown
high specificity on the U-87 MG cell lines. Cell culture studies demonstrated that the incorporation values of
131
I-PHT on the four cell lines decreased with increasing radioactivity. Also, incorporation values of 131I-PHT
on the four cell lines were found to be about 40 times higher than that of 131I. In addition, relative cell
survival values on four cell lines for PHT samples were obtained to be approximately 55-60% after 72 hours.
However, the slopes in 72 hours for PHT were high on all cell lines. This means that cytotoxicity increased
with increasing concentrations of PHT. Finally, according to the results of apoptotic effect, induction of
apoptosis could not be observed on cell lines. Consequently, 131I-PHT may be a good radiopharmaceuticals
for targeting radionuclide therapy of brain cancers.
Figure 1. Chemical structure of Phenytoin (PHT)
REFERENCES
1)M. A. Rogawski, W. Löscher. Nat. Rev. Neurosci.5(7) (2004) 553.
2)R. J Porter, A. Dhir, R. L. Macdonald, M. A. Rogawski. Handb. Clin. Neurol. 108 (2012) 663.
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AUTOMATED PRODUCTION AND QUALITY TESTING OF 18F-LABELLED
RADIOTRACERS USING THE BG75 SYSTEM
Atilio I. Anzellotti1, Aaron McFarland1, Jim BAILEY1, Doug Ferguson1
ABT Molecular Imaging Inc, Louisville, USA, [email protected]
1
The BG75 system comprises a small, positive ion cyclotron (7.5 MeV), synthesis and quality control modules.
All modules are self-shielded and automated with the possibility of being controlled by one operator from
one control console. Every radiotracer is produced in a single-use card that is sterile and represents a close
system (DOSE ON DEMAND); ultimately the final product is delivered aseptically into a sterile syringe.
Automated tests for quality control are performed in parallel to the dose manufacture and have been validated
according to ICH guidelines.1
The system has consistently produced clinical grade [18F]FDG doses since March 2013 in Sveta Marina
University Hospital (Bulgaria) passing all required Quality Control criteria. In addition [18F]FDG and
[18F]NaF have been produced in the University of Oklahoma – College of Pharmacy (USA)2,3 and
other sites all around the world since 2012. A summary of the results obtained for [18F]FDG and [18F]NaF
in our sites in addition to proof of concept for other tracers such as [18F]FMISO and [18F]FLT, will be also
presented.
REFERENCES
1)A.I. Anzellotti, A. R. McFarland, D. Ferguson, K.F. Olson, Curr. Org. Chem. 17 (2013) 2153.
2)V. Awasthi, J. Watson, H. Gali, G. Matlock, A. McFarland, J. bailey, A. Anzellotti, Appl Rad. Isot. 89 (2014) 167.
3)V. Awasthi, H. Gali, A. McFarland, A. Anzellotti, J Nucl Med. 55 (2014) 1243.
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INFLUENCE OF GAMMA RADIATION ON THE RELEASE OF THE CONTROLLED
DRUG POLYMER MATRIX
Jorge Gabriel dos Santos Batista1, Talita Aparecida de Moraes Vrechi1, Ademar Benévolo
Lugão1
Instituto de Pesquisas Energéticas e Nucleares (IPEN / CNEN - SP), São Paulo, Brazil, [email protected]
1
Gamma radiation has been used for various applications, which extend from research and commercial
manufacture area. With the use of gamma radiation to sterilize, the properties of materials may be also
modified. The present work is a study of the effects of gamma radiation on natural and synthetic polymer
matrices of loader drugs. The polymers used in the study were: regular starch, modified starch, chitosan
and polyvinylpyrrolidone (PVP), focusing their influence on the release of diclofenac sodium dose rate and
the dose of gamma radiation. This study did not aim at modeling the release of a drug through the use of
radiation but to evaluate the possibility of sterilizing and synthesize controlled release systems in the form of
hydrogels and membranes based polymers described above without interfering with degradation and release
of drug molecules as well as the polymers used. The results showed that radiation depending on the dose
used may interfere with the release and degradation of these systems, in addition to changing its mechanical
properties1,2.
REFERENCES
1) I.C. Jacobs, N.S. Mason, Polymer delivery systems concepts, in Polymeric delivery systems: properties and applications,
B.A. Charpentier, Editor, American Chemical Society: Washington, DC. 1993, p. 1-17.
2) N.A.. Peppas. et al.; Hydrogels in pharmaceutical formulations. Eur. J. Pharm. Biopharm. n.50, p. 27–46, 2002.
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I AND 123I PURIFICATION FOR BIOMOLECULES LABELING
131
Marcela Forli Catanoso1, João Alberto Osso Jr.2
Hospital Israelita Albert Einstein, 2International Atomic Energy Agency (IAEA), São Paulo, Brazil, [email protected]
1
Nuclear medicine is a medical area based on the use of radioactive isotopes as open radioactive sources
for diagnosis and therapy[1]. Iodine radioisotopes are commonly used in nuclear medicine in both diagnosis
and therapy for several diseases and can be used as unique tracer or labeled with organic compounds[2]. The
main iodine radioisotopes are 123I for thyroid study and diagnostic through the SPECT technique and 131I
used both in diagnosis and therapy due to its physical characteristics of decay by b- and its g-ray emissions
that are softened with the use of specific collimators for diagnosis[1]. The 123I is routinely produced at IPEN
in cyclotron[2] through the reaction: 124Xe (p, 2n) 123Cs -> 123Xe -> 123I and the 131I is routinely produced using
the nuclear reactor through the indirect reaction: 130Te (n,g) -> 131mTe -> 131Te -> 131I, irradiating compounds
containing Te[3]. The radiopharmaceuticals produced routinely at IPEN-CNEN/SP go through rigorous
quality control tests where chemical and radionuclidic purity of the primary radioisotopes are within the
permissible limits currently defined[4-6]. However, the presence of some contaminants can prejudice the
biomolecules labeling that will produce radiopharmaceuticals of first generation to the oncology area in
nuclear medicine. The aim of this work was to study a purification method of 123I and 131I radioisotopes
produced at IPEN, allowing the labeling of biomolecules. The methodology was separated on 3 steps:
Evaluation of 123I e 131I radionuclidic purity using a hiperpure germanium detector, chemical purity using
ICP-OES and the retention and elution study of 131I in several absorbers to choose the most appropriate for
the purification tests analyzing the behavior of the possible contaminants. The radionuclidic analyses showed
the presence of Te and Co radionuclides on 131I samples and Te, Tc e Co radionuclides on 123I samples. The
chemical purity analyses showed the presence of Al and Mo in 123I, coming from the window material of
the target holder and the presence of Al and Te in 131I samples, coming from the target holder and the target.
The retention and elution study selected the most promising adsorber to the purification technique, in this
case, the Dowex 50WX4 cationic exchange resin that showed an excellent 131I elution and the retention of
radionuclidic and chemical impurities present in the solution.
1. Thrall, J.H., Ziessman, H.A., Medicina Nuclear. 2a ed. Rio de Janeiro: Guanabara Koogan, 2003.
2. Schlyer, D.J. Production of radionuclides in accelerators. Handbook of Radiopharmaceuticals: Radiochemistry and
Applications.England, U.K.: John Wiley & Sons Ltd, 2003, p.1-70.
3. International Atomic Energy Agency: Manual for Reactor Produced Radioisotopes. Vienna, Austria. 2003. (IAEATECDOC-1340).
4. The United States Pharmacopeia. Official monographs: USP 30 Iodine, Sodium iodide I 123 Solution. Rockville, MD: The
United States Pharmacopeial Convention, NF 25, v.2, p.2371, 2007.
5. European Pharmacopoeia 5.0. Sodium iodide (123I) Injection. Strasbourg: Convention on the Elaboration of a European
Pharmacopoeia, v. 1, n.50, p.842-843, 2004.
6. Instituto de Pesquisas Energéticas e Nucleares. Documentação interna: Produção de Radioisótopos. 2009.
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DIRECT METHOD FOR ASSESSEMENT OF AMINOPOLYETHER
CONCENTRATIONS ON 18F-FDG SAMPLES
Renata Lins Carneiro Leão1, João Eudes do Nascimento1, Natalia Cassia do Espirito Santo
Nascimento1, Mércia Liane de Oliveira1
Centro Regional de Ciências Nucleares do Nordeste, Recife, Brazil, [email protected]
1
The 2 - [18F] Fluoro-deoxy-D-glucose (18F-FDG) has been synthesized successfully since 1976 and nowadays
it is the positron-emitting radiopharmaceutical most used in PET scans. In order to obtain more efficient
methods, several improvements on 18F-FDG production were implemented over the years. Regarding the
synthesis duration, the utilization of aminopolyether as catalyst make possible the reaction last 50 min
with a yield of over 50%. However, accurate methods to access the aminopolyether concentration in the
radiopharmaceutical should be used prior the injection of the drug into the patient. The quality control
methodologies for 18F-FDG are described at United States Pharmacopeia (USP)1, British Pharmacopeia
(BP)2 and European Pharmacopeia (EP)3. These compendia describe methodologies based on thin-layer
chromatography (TLC) to determine visually if the concentration of aminopolyether present in 18F-FDG
formulation is below the established limits. The objective of this study was to suggest a direct method to
determine the chemical purity of 18F-FDG, using TLC, and to validate this method in accordance to the
parameters established in the RE 899/20034 of ANVISA. For comparison, the chemical purity assay was
performed by following two methods: 1) developing the TLC plate in a solution of methanol and ammonia
(90:10) and exposing the developed plate to iodine vapor (according to USP), and 2) placing the TLC
plate directly on an iodine chamber. The chemical purity method with chromatographic run was sensitive
(DL: 0.014 mg/mL) and robust (average CV%= 2.84%). The method without chromatographic run, besides
being specific (only one spot was visualized corresponding to the FDG), demonstrated to be more sensitive
when compared to the chromatographic run test, showing a DL of 0.003 mg/mL, and faster. The methods
studied were effective, respecting the limits prescribed by ANVISA, and they can be used in routine with
the reliability of the results.
REFERENCES
1) Fludeoxyglucose F 18 injection. In: The United States Pharmacopeia, 33th ed., 2010.
2) Monographs: Radiopharmaceutical preparation, Fludeoxyglucose [18F] injection, 2000.
3) Fludeoxyglucose [F18] injection. European Pharmacopoeia, 7th ed., 2010.
4) Agência Nacional de Vigilância Sanitária. Resolução RE nº. 899: Guia para validação de métodos analíticos e bioanalíticos,
2003.
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OPTIMIZATION OF METHODOLOGY FOR THE DETERMINATION OF GROSS
ALPHA AND BETA ACTIVITY IN WATER BY LSC
Ademar de Oliveira Ferreira1, Marcelo Bessa Nisti1, Cátia Heloisa Rosignoli Saueia1, Barbara
MAZZILLI1
Laboratório de Radiometria Ambiental, Instituto de Pesquisas Energéticas e Nucleares (IPEN), São Paulo, Brazil,
[email protected]
1
The approach taken in the WHO Guidelines for controlling radiological hazards in public water supplies has
two stages. The first is an initial screening for gross alpha and beta activity to determine whether the activity
concentrations (in Bq/litre) are below levels at which no further action is required; and if these screening
levels are exceeded, investigation of the concentration of individual radionuclides and comparison with
specific guidance levels. The classical approach consists of evaporating a known volume of water and
measure the activity of the residue in a glass flow proportional counter. An attractive alternative to classical
methods is the ultra-low level liquid scintillation counting (LSC) coupled to alpha–beta discrimination,
which allows a rapid and simple determination of gross alpha and beta activities, which are simultaneously
measured. This paper aims to establish the best experimental conditions to determine gross alpha and beta
activity in water by LSC, using a 1220 Quantulus™ Ultra Low Level Liquid Scintillation Spectrometer. Two
scintillation cocktails were used, Ultima Gold AB and Optiphase Hisafe 3, mixed with the sample in three
different ratios: 10/10, 08/12 and 05/15. The following parameters were studied: Pulse Shape Discrimination
(PSA), efficiency, Minimum Detectable Activity (MDA), Figure of Merit (FOM) and Factor of Merit (FM).
The best PSA obtained was 90 for all the combinations of cocktails. The verification of the efficiency was
performed by measuring standard solutions. The best performance was achieved by using the scintillation
cocktail Ultima Gold AB with the ratio 08/12 and by using the Optiphase Hisafe 3 with the ratio 05/15.
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DETERMINATION OF THE RADIATION DOSE IN THE OPERATOR POSITION IN
MAMMOGRAPHY EQUIPMENT
Jacqueline Sales Barreira1, Sarah Damasceno Pinheiro Huet1, Vitor Vivolo1
Instituto de Pesquisas Energéticas e Nucleares - IPEN/CNEN, São Paulo, Brazil, [email protected]
1
The use of X-rays beams for use in diagnostic radiology is very common and important to Medicine,
including mammographic diagnosis.
The evaluation of the radiation dose given to the patients and workers are very important to protect them of
the deleterious effects of ionizing radiation.
The Instruments Calibration Laboratory (LCI) of the IPEN-CNEN/SP performs for many years the calibration
of the dosimeters (using standard X-ray beams) applied in radiation dosimetry (in diagnostic radiology). The
objective of this paper is performs measurements to determine the dose in the mammography equipment
(VMI Graph Mammo AF Philips) operator, behind the safety glass (in the panel control position). After that
initial procedures it will be realized the evaluation if the lead glass is effective for a protective barrier against
scattered radiation emitted during a calibration and examination routines, or if it is required another form of
physical protection for the workers during operation of the mammographic equipment.
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DETERMINATION OF RADIATION DOSE IN SURFACE BREAST USING TWO TYPES
OF PMMA SIMULATORS
Jacqueline Sales Barreira1, Sarah Damasceno Pinheiro Huet1, Vitor Vivolo1
Instituto de Pesquisas Energéticas e Nucleares - IPEN/CNEN, São Paulo, Brazil, [email protected]
1
The use of X rays for diagnostic radiology is very common and important to Medicine, including
mammographic diagnosis.
Evaluate the radiation dose given to patients is very important to protect them the deleterious effects of
ionizing radiation.
The Instruments Calibration Laboratory (LCI) of IPEN perform calibration in dosemeters used in radiation
dosimetry (in diagnostic radiology) for many years.
The objective of that paper were the measurements of the dose given in the surface breast, using VMI Graph
Mammo AF Phillips and two simulators made of PMMA (poly methyl methacrylate), one based on the
IAEA TRS 457¹, and another based on the standard IEC 61267².
This results is very important to control quality program of mammography equipment.
REFERENCES
1) International Atomic Energy Agency. Dosimetry in Diagnostic Radiology: An International Code of Practice. IAEA, Vienna,
2007 (Technical Report Series No. 457).
2) International Electrotechnical Commission. Medical Diagnostic X-ray Equipment – Radiation Conditions for use in the
Determination of Characteristics, IEC 61267, Geneva, 2005.
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DOSIMETRIC EVALUATION OF INHOMOGENEITY EFFECTS IN THE SPINAL
CORD
Andre Lima de Souza Castro1, Larissa Thompson1, Hugo Leonardo Lemos Silva2, Tarcísio
Passos Ribeiro Campos1
Universidade Federal de Minas Gerais, 2Santa Casa de Miserocórdia, Belo Horizonte, Brazil, [email protected]
1
The human body consists of a variety of tissues and cavities with diferent physical and radiological properties.
The presence of these inhomogeneities will produce changes in the dose distribution, depending on the
amount and type of material present and on the quality of radiation. The aim of this paper is to investigate
the influence of the vertebral column on the absorbed dose along the spinal cord. The methodology consisted
on developing a simplified equivalent tissue material phantom for dosimetric studies of bone tissue
inhomogeneity. The detector used in this paper was the radiochromic film EBT-2, developed for measuring
absorbed doses of radiation used in high energy radiotherapy for a wide dose range from 0,01 Gy to 40,0
Gy. The radiotherapy planning of the phantom was performed by Soma Vision / CadPlan Varian Medical
Systems software. The dosimetric results measured in the film were therefore compared to those predicted
by the treatment planning system and suggested an increase in absorbed dose in bone-tissue interface.
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Evaluation of profenofos in aqueous solution by electrons beam
Flávio Thihara Rodrigues1, Eric Marchioni2, Sonia Lordel2, Florent Kuntz3, Anna Lucia
Casañas Haasis Villavicencio1, Diane Julien-David2
Instituto de Pesquisas Energéticas e Nucleares (IPEN-CNEN/SP), Centro de Tecnologia das Radiações, 2IPHC, UMR 7178,
Equipe de Chimie Analytique des Molécules BioActives-Université de Strasbourg, Faculté de Pharmacie, 3Aérial, Centre de
Ressources Technologiques, Parc d’Innovation, São Paulo, Brazil, [email protected]
1
Profenofos is an organophosphate insecticide used widely in Brazil for controlling pests of corn, soybeans,
coffee, tomato, cotton, beans, potatoes and others. Irradiation is process largely technique used worldwide
and recommended by many health agencies for preservation of foods that uses gamma rays, X-rays or
accelerated electrons. Food irradiation has been extensively applied for the treatment of various food
products, reducing pathogens, replacing chemical fumigants and an important technology in food Industry.
The purpose of this present research were evaluated the effect of E-beam on profenofos aqueous solutions.
The samples were irradiated with a electrons beam accelerator, exposed doses of 0 (control), 4.6, 11.7 and
31.6 kGy. Furthermore, degradation of profenofos after irradiation treatment were qualitatively determinated
using gas chromatography coupled mass spectrometry (GC-MS). E-beam treatment with radiation dose 31.6
kGy promoted reduction of 93.40% profenofos solution.
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MONITORING OF ENDS WORKERS EXPOSED POSITRON EMITTERS
Natalia Cassia do Espirito Santo Nascimento1, Êudice Correia Vilela1, Mércia Liane de
Oliveira1
Centro Regional de Ciências Nucleares, Recife, Brazil, [email protected]
1
The increasing amount of applications using non-sealed positron-emitting sources requires the completion
of a thorough dosimetric monitoring of workers exposed to these types of radiation. These exposures occur
principally in the fingers and hands, because these are body parts that are in direct contact or very close to
the radiation source. This paper aims establishing a methodology for calibration of extremities dosimeters
based LiF: Mg, Ti (TLD-100) for use in mixed beams of radiation. For this, we used the dosimetric system
XD EXT-RAD-100, manufactured by Harshaw (now Thermo Scientific). The dosimeters were irradiated on
acrylic phantom finger. In order to analyze the performance of the dosimetric system used, tests were made
with individual sensitivity, batch homogeneity, reproducibility, beta and photon energy response and angular
response, according to the recommendations of ISO 12794. Subsequently, the dosimeters were calibrated
in standard beams of beta radiation (using a source of 90Sr +90Y) and gamma (using a source of 137Cs).
The calibration of the dosimeters was carried in terms of Hp (0.07). To simulate the working environment
of monitored individuals, tests were carried out in mixed radiation fields. The batch of dosimeters used
in this study showed a value of homogeneity better than 6.9% and reproducibility better than 4.8%. The
study of angular response of the dosimeters showed acceptable variation of the response (less than 15%),
demonstrating its utility for dosimetry of extremities. The test of beta and photon energy response also
presented according to ISO 12794, because the variation of TL response was less than 50% in the whole
energy range considered. The results for tests carried out in mixed radiation beta-photon fields suggest that
for use of extremity dosimeters EXT-RAD XD-100 type in mixed fields of beta-radiation photons, the most
appropriate methodology for calibration is irradiating them with a source 137Cs standard. Considering these
results, we can conclude that the EXT-RAD XD-100 dosimetric system meets the necessary requirements
for application in monitoring the ends of individuals occupationally exposed to mixed radiation beta-photon
fields.
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poster session
2
Nuclear and Radiochemistry
4th-INCC 2014 I 4th International Nuclear Chemistry Congress
RADIOLABELLING OF NANOPARTICLES AND ITS USE FOR TRANSPORT STUDIES
Karsten Franke1, Stefan Schymura1, Heike Hildebrand1, Johannes Kulenkampff1
Dept. Reactive Transport, Institute of Resource Ecology, Helmholtz-Zentrum Dresden-Rossendorf, Leipzig, Germany, k.franke@
hzdr.de
1
Hundreds of products containing nanoparticles (NP) are already in use. Nanotechnological innovation
is identified in many sectors, including public health, employment and occupational health and safety,
information society, industry, environmental protection, fuel and energy generation, transportation, security
and space exploration. But the new materials may also pose risks to the environment and raise health
and safety concerns. These risks have been addressed in several ongoing research projects. The overall
conclusion so far is that, even though NP are not per se dangerous, there still is scientific uncertainty about
the safety of NP in many aspects and therefore the safety assessment of the substances must be done on a
case-by-case basis.
A key factor for the fate of NP in the environment and their introduction into the food chain is the bioavailability
and thereby the mobility of the NP. Multiple factors control the migration behaviour of the NP in water and
water saturated/unsaturated soils. Reversible and irreversible physical and chemical interactions cause a
complex scenario with a great variety of boundary conditions. The transport of NP through soil, water and
sediments is influenced by advection, diffusion, retardation due to sedimentation, filtration, staining, size
exclusion effects, aging due to chemical corrosion, sorption and aggregation.
The experimental access to transport studies requires the observation of NP in complex environmental
media at naturally relevant concentrations. This is a major challenge in laboratory work which can be
overcome by the use of radiotracers.
In this work we present different techniques for the introduction of the radiotracers into the NP (Ag0,
TiO2, MWCNT) including activation of NP, radiosynthesis of NP, radiolabelling of NP, self-diffusion of
radioisotopes into NP and recoil labeling (1, 2, 3). The radiolabelled NP were used for 1D and 4D (time
resolved Positron Emission Tomography (PET)) transport studies. The first results of the transport studies
(BTC- break through curves and PET images) will be given as prove of principle.
The use of radiotracers allowed the easy online and in-situ access to NP in environmental media and enabled
systematic investigation of key process parameters for NP transport behavior.
REFERENCES
1) H. Hildebrand, K. Franke, J. Nanopart. Res. 14 (2012) 1142.
2) K. Abbas et al., J. Nanopart. Res. 12 (2010) 2435.
3) U. Holzwarth et al., J. Nanopart. Res. 14 (2012) 880
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MUON SCIENCE: PROVIDING A FACTOR OF 36 IN H-ATOM ISOTOPIC MASS
Donald G. Fleming1, P. B. Bakule2, B. C. Garrett3, S. L. Mielke4, D. G. Thruhlar4
TRIUMF, Vancouver, BC, Canada 2Physics Institute, Prague, Czech Republic, 3Pacific Northwest Nat. Lab, Richland, WA,
USA, 4Dept. of Chemistry, Univ. of Minnesota, MN, USA, Vancouver, Canadá, [email protected]
1
Since the discovery of deuterium (D) by Harold Urey in 1932, isotopic effects have played a central role in
the chemical and biological sciences. Though radio-labeling of different isotopes has been known for many
years, the largest effects are to be found at the lowest end of the mass scale, and notably for the isotopes
of the H atom. However, D differs by only a factor of two in mass compared to H, and tritium, though
three times the mass, is dangerously radioactive, and as such has seen only limited use experimentally and
primarily in the realm of “hot atom” reactivity using radio-analytical techniques1. It is from muon science
that we have been able to extend the isotopic H atom mass scale. The muon comes in two charge states,
m- and m+, particle and anti-particle, respectively. Muons are produced 100% spin-polarized at a nuclear
accelerator (TRIUMF) from pion (p-, p+) decay, a parity-violating process. The subsequent decay of the
muon is also via the weak interaction, emitting an e- or e+ preferentially along the muon spin direction, with
a mean life of 2.2 ms. (The m+ lifetime is independent of its environment, but that for the m- depends on the
nuclear charge, Z). This weak-interaction decay underpins the basic mSR (muon spin rotation) technique,
wherein the muon is stopped in a transverse magnetic field, where it undergoes Larmor spin precession at a
characteristic frequency, with its decay e-, e+ detected by a fixed set of counters in the plane of precession,
exhibiting then characteristic oscillations. The damping of these oscillations is due to the interaction of the
muon spin with its environment, and is analagous to a T2 relaxation process in NMR.
When the positive muon stops in matter, it forms the `muonium’ atom (Mu = m+ e-), with a mass of 0.114
amu, the lightest isotope of the H atom. (The m+ is only 1/9 th the proton mass, but it is 200 times the electron
mass.) When the negative muon stops in matter it forms a `muonic atom’, and in helium it forms the muonic
He atom (Hem = [4Hem-]+ e-), with an atomic mass of 4.11 amu, and is the heaviest isotope of the H atom2.
Muon science and the techniques of nuclear science thus allows us to compare the effects of H-atom isotopic
mass over a remarkable factor of 36 in atomic mass.
The importance of this will be illustrated by comparisons between rigorous quantum rate theory and
experiment for the thermal reaction rates of Mu + H2 and Hem + H22 and of the state-selected reaction of
Mu with H2 (v=1), where H2 is produced in its first vibrational state by stimulated Raman pumping3. The
agreement between theory and experiment is essentially within experimental error, an unprecedented result
over such a change in mass.
REFERENCES
1) D.G. Fleming, Rad. Phys. Chem. 28 (1986) 115.
2) D.G. Fleming, D.J. Arseneau, O. Sukhorukov, J.H. Brewer, S. L. Mielke, G. C. Schatz, B.C. Garrett, K.A. Peterson, and
D.G. Truhlar, Science 331 (2011) 448; J. Chem. Phys.,135 (2011) 184310.
3) P. Bakule, D.G. Fleming, O. Sukhorukov, K. Ishida, F. Pratt, T. Momose, E. Torikai, S.L. Mielke, B.C. Garrett, K.A.
Peterson, G.C. Schatz, and D.G. Truhlar, J. Phys. Chem. Lett. 3 (2012) 2755.
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4th-INCC 2014 I 4th International Nuclear Chemistry Congress
A NEW METHOD FOR THE DETERMINATION OF 226Ra BY ALPHA
SPECTROMETRY
Giovani Bergamini1, Maria Helena Tirollo Taddei1, Mychelle Munyck Linhares Rosa1, Marcelo
Tarquínio Ferreira1, Luan Teixeira Vieira Cheberle1, Sandra Maria Cheberle dos Santos1,
Neide Aparecida Mariano2, Erika Coaglia Trindade Ramos2
Brazilian Nuclear Energy Commission / Poços de Caldas Laboratory (CNEN / LAPOC), 2Federal University of Alfenas (UNIFAL/
MG), 8Federal University of Alfenas (UNIFAL/MG), Poços de Caldas, Brazil, [email protected]
1
A new method for the determination of 226Ra by alpha spectrometry is described. The method uses 225Ra
as yield tracer, which is in radioactive equilibrium with its parents 229Th. Radium was purified through
radiochemical procedures using Ln resin and cationic exchange resin and then electrodeposited on a stainless
steel disc from solution of ammonium oxalate, and counted by alpha spectrometry. Estimation of 225Ra in the
alpha spectra is made via measurement of its alpha-emitting daughters, 217At being the most indicated to this
purpose. This method produced spectra with excellent resolutions and excellent recovery yields of 226Ra.
Furthermore, the method allows significant reduction in the time required for the determination of 226Ra in
drinking water samples, around 4 days, in comparison with other methods, which can reach 20 or 38 days
to quantify this radionuclide.
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
MODULATION OF ALBUMIN EXPRESSION OF PLASMA IN RATS INDUCED BY
RADIATION
Celso Vieira de Lima1, Patrícia Falcão1, Tarcisio Passos Ribeiro de Campos1
Departamento de Ciências e Técnicas Nucleares, Engenharia Nucelar, Universidade Federal de Minas Gerais (UFMG), Belo
Horizonte, Brazil, [email protected]
1
The objective of this research is to investigate and quantify the modulation of expression of plasma proteins
in radiation-induced rats. This change is reported to plasma albumin according to the whole body radiation.
Watchman rats were 12 to 16 weeks of age with a body weight range of 300-380 g, with a photoperiod of 12
h with free access to water and food. These animals were subjected to treatment with radiation cobalt source
at a dose of 5 Gy, and the periods of 12, 24, 48, 72 and 96 h after treatment with radiation. These animals
were anesthetized and under anesthesia, these thoracic and abdominal laparotomies were performed, and
then 1 mL of blood was collected from cava vein, renal vein, splenic vein, jugular vein and pulmonary
vein. The blood was heparinized and then separated by centrifugation (2500 rpm / 30 min). The plasma
was separated, aliquots were subjected to SDS / PAGE 10% process. The gels were subjected to staining
process. The images were scanned and analyzed with Image J. software. There was a marked reduction
in the concentration of the protein albumin in the blood in almost all regions studied compared to the
albumin concentration of the rats control group, not treated with radiation. Our data have showed reduction
of the albumin expression in the blood of the 5 Gy total body irradiated rats. This fact contributes to the
worsening of side effects of this treatment because albumin is the major blood protein and it is responsible
for controlling blood osmolarity and much of the transport of substances such as hormones, nutrients and
drugs.
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4th-INCC 2014 I 4th International Nuclear Chemistry Congress
DETERMINATION OF 234U, 235U, 238U, 228Th, 230Th, 232Th, 226Ra, 228Ra, and 210Pb IN FOODS
OF THE BRAZILIAN TOTAL DIET
Mychelle Munyck Linhares Rosa1-2, Maria Helena Tirollo Taddei1, Luan Teixeira Vieira
Cheberle1, Marcelo Tarquinio Ferreira1, Sandra Maria Cheberle Santos1, Roseane P.
Avegliano2, Vera Akiko MAIHARA2, Giovani Bergamini
Laboratório de Poços de Caldas (CNEN/LAPOC), 2Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), Poços de
Caldas, Brazil, [email protected]
1
The activity concentrations of 234U, 235U, 238U, 228Th, 230Th, 232Th, 226Ra, 228Ra, and 210Pb were determined
in food groups of the Brazilian Total Diet (TDS). In this study, the TDS was based on the evaluation of
food representing a Market Basket, which reflected the dietary habits of the São Paulo State population,
corresponding to 72% of the average food consumption for the state of São Paulo. The food consumption
data and information were obtained from the National Household Food Budget Survey conducted by the
Brazilian Institute for Geography and Statistics in 2002-2003, which included 5,440 foods. For selection of
the foods in this TDS only the food consumed more than 2 g/day/person, except fish were considered. This
resulted in 71 foods grouped in 30 food groups. To determine 226Ra, 228Ra, and 210Pb activity concentrations
a radiochemical separation using sulphate co-precipitation followed by total counting in a gas flow
proportionally low background was developed. The U and Th isotopes were determined by anion exchange
and chromatographic resin for purification followed by alpha spectrometry. From the radiological point of
view the determination of these radionuclides is relevant because they are decay products of the natural
series of 238U and 232Th, being responsible for the natural radioactive exposures of man. The results showed
that a low activity concentration can be detected in the food samples analyzed
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
SOIL-TO-PLANT TRANSFER FACTORS FOR RADIONUCLIDES IN SAMPLES OF
LEMON BALM (MELISSA OFFICINALIS) COMMONLY USED AS A MEDICINAL
PLANT
Fábio Vitório Sussa1, Marcos Medrado de Alencar1, Barbara P. MAZZILLI1, Paulo S. Cardoso
da SILVA1
Instituto de Pesquisas Energéticas e Nucleares (IPEN – CNEN/SP), São Paulo, Brazil, [email protected]
1
In recent decades, the study of medicinal plants has become the focus of ever more extensive research
all over the world, due to diversity and potential that medicinal plants have as source of medicinal
products. Generally, studies related to medicinal plants aims to characterize the active compounds of the
plant for scientific evidence of their therapeutic properties. However, studies of the 238U and 232Th natural
radionuclides series distribution in such plants are sparse. A medicinal plant containing high concentrations
of natural radionuclides can cause health problems, since it is commonly used over long periods. Lemon
balm (Melissa officinalis Linn.) is a medicinal and aromatic herb popularly used to make tea, which serves
as a sedative, promote sleep, and stress and anxiety reduction. The objective of this work was to determine
the concentration of naturally occurring radionuclides 238U and 232Th series, primarily focusing on the
determination of soil-to-plant transfer factors (TF) for Lemon balm samples. The plants were obtained from
the seeds, transferred after three months to field conditions. The essays were carried out in the Municipal
Gardening School experimental area, in Ibirapuera Park, São Paulo, Brazil. The experimental design was
completely randomized, being three cropping systems (control, organic and conventional) and two types
of fertilization (presence and absence of microelements). The transfer factors for natural uranium (238U
and 234U) and thorium (232Th and 230Th) isotopes were obtained in Lemon balm samples harvested at two
distinct times (summer/outumn and autumn/winter). The content of U and Th isotopes in Lemon balm
leaves and soil was determined by alpha spectrometry after radiochemical separation by ionic exchange
resins and measurement with a silicon surface-barrier detector. Reference materials IAEA-300 and IAEA326 were used for quality control of the measurements. The results were submitted to analysis of variance
and compared by the Tukey test (p<0.05) using the software Statistic.
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4th-INCC 2014 I 4th International Nuclear Chemistry Congress
STANDARDIZATION OF 18F BY LIQUID SCINTILLATION SPECTROMETRY WITH
THE CIEMAT/NIST 3H-STANDARD EFFICIENCY TRACING METHOD
Maria da Conceição de Farias Fragoso1, Emerson Emiliano Gualberto de FARIAS2, Mércia L.
de Oliveira1, Elvis Joacir de FRANÇA1, Eliane V. Honorato1, Fernando Roberto de Andrade
Lima1
Centro Regional de Ciências Nucleares do Nordeste - CRCN-NE -Comissão Nacional de Energia Nuclear (CNEN), Camaragibe,
Brazil, [email protected]
1
Every day, the Positron Emission Tomography (PET) technique plays a more important role on medical
diagnosis. Molecules labeled with 18F are already widely utilized routinely, but new radiotracers (11C, 68Ga,
82
Ru, 13N) are also utilized at nuclear medicine centers (NMC). In the field of the radionuclide metrology, the
biggest challenge now is to provide adequate standards of these short half-lives radionuclides to calibrate
detectors (activimeter and PET Scans) at NMC. Among the existing alternatives for the standardization
of radioactive sources, the 4pb Liquid Scintillation Spectrometry Method with 3H-Standard Efficiency
Tracing (also known as CIEMAT/NIST method) is being increasingly utilized. This technique is based on a
combination of theoretical calculations of the counting efficiency with the experimental data obtained from
a liquid scintillation spectrometer1,2. The principal advantage of the CIEMAT/NIST method is that only
standards of 3H are required, that is, no standards of the radionuclide to be analyzed are needed. In this work,
the procedure employed to standardize 18F and 68Ge solutions by the CIEMAT/NIST method is presented.
Confirmatory measurements were carried out with gamma spectrometry using high purity germanium
(HPGe) detector. In addition, the reference sources checked by these methods were used to calibrate and
test the radionuclide calibrators from Divisão de Produção de Radiofármacos (DIPRA), Centro Regional
de Ciências Nucleares do Nordeste (CRCN-NE). The results obtained by the two techniques were in good
agreement, demonstrating that the CIEMAT/NIST method is a reliable tool for the activity determinations
of these short halflives radionuclides.
REFERENCES
1) B. E. Zimmerman, J. T. Cessna, M.P. Unterweger, Appl. Radiat. Isotopes 56 (2002) 315.
2) R. I. Dobrin, M. Pavelescu, C.N. Dulama, Rom. Journ. Phy. 56 (2011) 1148
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Nuclear and Related Techniques
4th-INCC 2014 I 4th International Nuclear Chemistry Congress
SEMICONDUCTOR OXIDE EVALUATION OF MECHANICAL AND LASER MARKED
ASTM F139 STAINLESS STEEL VIA HYPERFINE INTERACTIONS AND MOTTSCHOTTKY TECHNIQUES
Eurico Felix Pieretti1, Artur W. Carbonari1, Fabio H. M. Cavalcante1, Elisabete Jorge
Pessine1, Olandir Vercino Correa1, Tomaz Puga Leivas2, Maurício David Martins das Neves1
Instituto de Pesquisas Energéticas e Nucleares (IPEN-CNEN/SP), 2Instituto de Ortopedia e Traumatologia do Hospital das
Clínicas da Faculdade de Medicina da Universidade de São Paulo (IOT/HCFMUSP), São Paulo, Brazil, [email protected]
1
The investigation on the corrosion resistance of biomaterials and the effects of manufacturing processes,
including marking for traceability, is extremely important to evaluate whether the surface modification
caused by the laser treatment affects theirs electrochemical properties. The engraving process by laser beam
has been used to ensure the identification and traceability of orthopedic implants. This study evaluates the
influence of the laser parameters, specifically the pulse energy and speed rate, on the corrosion resistance of
the ASTM F139 austenitic stainless steel (SS), treated via Nd: YAG laser beam, by electrochemical methods.
The electrolyte used was a phosphate buffered solution (PBS), with pH 7.4, at 37 °C. This biomaterial’s
electronic properties were evaluated by Mott-Schottky approach. The results showed that the alternating
laser parameters changes the protective properties of the oxide layer, dislocates its flat band potential and
influences its susceptibility to localized corrosion. These results were confirmed by the hyperfine interactions
(HI) nuclear technique, which evaluated the semiconductor properties of the SS passive film.
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
ENHANCING NAA RESULTS BY USING ROBUST STATISTICS
Guilherme Soares Zahn1, Frederico Antonio Genezini1, Marcello Secco1, Regina Beck
Ticianelli1, Ana Maria Graciano Figueiredo1
Instituto de Pesquisas Energéticas e Nucleares – IPEN-CNEN/SP, São Paulo, Brazil, [email protected]
1
ABSTRACT
Neutron Activation Analysis (NAA) is an analytical technique where an unknown sample is submitted to
a neutron flux in a nuclear reactor, and its elemental composition is calculated by measuring the induced
activity produced. By using the relative NAA method, one or more well-characterized samples (usually
certified reference materials - CRMs) are irradiated together with the unknown ones, and the concentration
of each element is then calculated by comparing the areas of the gamma ray peaks related to that element.
When two or more CRMs are used as reference, the concentration of each element can be determined by
several different ways, either using more than one gamma ray peak for that element (when available), or
using the results obtained in the comparison with each CRM. Therefore, determining the best estimate for
the concentration of each element in the sample can be a delicate issue.
In this work, samples from several CRMs were irradiated together and the elemental concentration in one
of them was calculated using the other as reference. Two sets of peaks were analyzed for each element: a
smaller set containing only the literature-recommended gamma-ray peaks and a larger one containing all
peaks related to that element that could be quantified in the gamma-ray spectra; the most recommended
transition was also used as a benchmark. The resulting data for each element was then reduced using up to
five different statistical approaches: the usual (and not robust) unweighted and weighted means, together
with three robust means: the Limitation of Relative Statistical Weight (LRSW), Normalized Residuals (NR)
and Rajeval (RT). The resulting concentration values were then compared to the certified value for each
element, allowing for discussion on both the performance of each statistical tool and on the best choice of
peaks for each element. The analysis of the Z-Scores and relative uncertainties obtained with each method
shows that the best results are obtained using the recommended gamma-ray set and either the Normalized
Residuals or the Rajeval techniques.
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4th-INCC 2014 I 4th International Nuclear Chemistry Congress
INSTRUMENTAL NEUTRON ACTIVATION ANALYSIS OF KILOGRAM-SIZED
SAMPLES OF DOG FOOD
Camila Elias1, Anneke Koster-Ammerlaan2, Elisabete A. De Nadai Fernandes1, Peter
Bode3, Márcio Arruda Bacchi1
Centro de Energia Nuclear na Agricultura (CENA), Universidade de São Paulo (USP), 2Human Resource Management, Delft
University of Technology (TUDelft), 3Radiation Science and Technology, Delft University of Technology (TUDelft), Piracicaba,
Brazil, [email protected]
1
Large sample neutron activation analysis (LS-NAA) allows obtaining better analytical representativeness
compared to the routinely practised small size sample analysis. Analysis of kilogram-sized samples can be
especially advantageous when homogenization is not feasible or when large objects cannot be damaged for
sampling purposes. Dog food is a complex material, composed of several different ingredients added to
provide complete nutrition. Therefore, taking small samples representative of an entire production lot can
be a quite critical step and may compromise the quality of results. In this work, LS-NAA and conventional
NAA were applied to study the representativeness of small test portions (350 mg) of dry dog food collected
from regular 1 kg packed bags. Twenty-four bags from one specific brand and one production lot were
acquired in a pet-shop in Delft, The Netherlands. The entire content of each bag was analyzed using the
large sample NAA facilitiy at the Hoger Onderwijs Reactor of the Delft University of Technology. After
particle size reduction in a knife mill, test portions of 250 mg from each of the 24 bags were packed in
polyethylene vials for conventional NAA at CENA/USP and irradiated in the IEA R1 nuclear research
reactor, IPEN/CNEN, São Paulo, Brazil. Br, Ca, K, Na and Zn could be measured by both LS NAA and
conventional NAA. Within bag and between bag variation of the chemical elements were assessed. Except
for K, the standard deviation of the mass fractions in the 24 large samples was higher than can be explained
from the uncertainty of measurement, indicating differences of composition amongst the dog food bags.
However, only for Zn the difference can be considered relevant (rsd = 15.5%), while for Br, Ca, K and Na
the relative standard deviations were lower than 6%. The variability of results obtained from conventional
NAA agreed well with that from LS-NAA. The agreement of results from LS NAA and conventional NAA
could confirm the representativeness of the small portions for measuring Br, Ca, K and Na.
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
ZINC MAPPING IN HUMAN PROSTATE SPHEROIDS USING X-RAY
MICROFLUORESCENCE
Roberta Gama Leitão1, Carlos A. N. Santos2, Antonio Palumbo Jr3, Pedro A. V. R. Souza4,
Catarine G. L. Canellas5, Marcelino José dos Anjos6, Luiz E. NASCIUTTI7, Ricardo Tadeu
Lopes8
Laboratório de Instrumentação Nuclear, (PEN / COPPE / UFRJ), 2Laboratório de Biotecnologia (Bioengenharia / DIPRO /
INMETRO), 3Laboratório de Interações Celulares (ICB / CCS / UFRJ), 4Serviço de Urologia, Hospital Federal do Andaraí,
5
Serviço de Urologia, Hospital Federal do Andaraí, 6Universidade do Estado do Rio de Janeiro, 7Instituto de Física (UERJ),
8
COPPE/UFRJ, Rio de Janeiro, Brazil, [email protected]
1
In this work we analyzed prostate cell spheroids treated with different concentrations of zinc using
synchrotron radiation X-ray microfluorescence (SRµXRF). Were analyzed human prostate spheroids of
benign prostate hyperplasia cell (BPH) and cancer cell line (DU145). The measurements were performed in
standard geometry of 45° incidence, exciting with a white beam and using an optical capillary with 20 μm
diameter collimation in the XRF beam line at the Synchrotron Light National Laboratory (Campinas, Brazil).
The results showed non-uniform distribution of Zn in all the spheroids analyzed. The results showed that the
differential response to zinc in DU145 cells suggests that there is a relationship between the carcinogenic
process and zinc levels.
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4th-INCC 2014 I 4th International Nuclear Chemistry Congress
LEAD IN THE ENVIRONMENT OF THE METROPOLITAN ZONE OF THE TOLUCA
VALLEY, IN MEXICO
Trinidad Martínez Castillo1, Graciela Zarazúa Ortega2, Alberto Fernández Alarcón1, Ciro
Márquez Herrera1, Samuel Tejeda Vega2, Pedro Ávila-Pérez2, Josefina Poblano-Bata3
Facultad de Química, Departamento de Química Inorgánica y Nuclear, Universidad Nacional Autónoma de México, 2National
Institute of Nuclear Research, 3Autonomous University of México State, México, Mexico, [email protected]
1
The Metropolitan Zone of Toluca Valley (MZTV) is Mexico’s the fifth largest metropolitan zone. Lead
concentration was measured by Total Reflection X-ray fluorescence (TXRF) and Inductively Coupled
Plasma Optical Emission Spectrometry (ICP-OES) in environmental samples of moss, division Bryophytes1,
soil dust, particulate matter, gasoline, diesel, water and coal of the Metropolitan Zone of Toluca Valley.
Moss, soil and dust samples showed highest lead concentration in Toluca downtown, Reforma Alameda
and southward Tollocan industrial corridor. Enrichment factors > 10, extremely highly enriched with
anthropogenic lead > 87% was found in moss, probably coming out from anthropogenic sources,
fossil fuel combustion processes and industrial sources2. In spite that lead aerosol concentrations were
lesser in downtown monitoring station, they were high in both south and north monitoring stations because
of meteorology and north-to-south wind. According to Enrichment factors (EF) and Geoacumulation
index IGeos, soils vary from uncontaminated to moderately contaminated. The experimental results for the
Reference Standard Materials and samples showed that digestion procedures and different used techniques
provide reproducible and accurate data for lead in environmental samples. There was a very good Pearson
correlation R2> 0.9 with slope of 1.1 between TXRF and ICP-OES values, with α 0.05.
REFERENCES
1)G. Zarazúa-Ortega, J. Poblano-Mata, S. Tejeda, P- Ávila. Pérez, C. Zepeda-Gómez, H. Ortiz-Oliveros, G. Macedo-Miranda.
Scientific World Journal, 2013, Article id 426492, 7pp. http://dx.doi.or/10.1155/203/426492
2)T. Martínez, J. Lartigue, F. Juárez, P. Ávila-Pérez, C. Márquez, G. Zarazúa, S. Tejeda.
J. of Radioanal. and Nucl. Chem. 273, 3 (2007) 577-582.
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RARE EARTH ELEMENT ASSESSMENT IN A SEDIMENTARY PROFILE FROM
JURUMIRIM RESERVOIR, SÃO PAULO STATE, BRAZIL, BY NAA AND ICP-MS
Sharlleny Alves Silva1, Robson Leocadio Franklin1, Déborah I. T. FÁVARO2, Wanilson
Luiz-Silva3
Setor de Química Inorgânica - ELAI - Companhia Ambiental do Estado de São Paulo, 2Laboratório de Análise por ativação
Neutrônica - LAN-CRPq, Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN – SP), 3Departamento de Geologia e
Recursos Naturais – DGRN, Instituto de Geociências, UNICAMP , São Paulo, Brazil, [email protected]
1
There is a growing interest in the quantification of contaminants in sediments originating from anthropogenic
activities. However, there are many elements that are not commonly monitored in the environment and are
being increasingly used in various industrial sectors1. Besides heavy metals, the interest in the determination
of three rare earth elements especially (Gd, Tb and Yb) has increased considerably over the last few years.
Rare Earth Elements (REE), in general, have been widely used in the production of CDs, TVs and as a
contrast in Nuclear Resonance Magnetic Imaging Tests. A research project is being developed between
CETESB (Environmental Company of São Paulo State) and IPEN in 3 important water supply reservoirs in
the São Paulo State, for a wide ranging evaluation of rare earth elements, in sediment and pore water samples.
In the present study the preliminary results for the Armando Avellanal Laydner reservoir, better known as
the Jurumirim reservoir, are presented. Its operations for generating electrical energy started in 1962. It
has a drainage area of 17.8 thousand km², with an extension of approximately 100 km in Paranapanema
River and 40 km in the Taquari river. The basin occupation is characterized by a drainage area with 14%
occupied by preserved vegetation, and therefore was chosen as a probable reference point for obtaining
values that can be used as REE background values for this region, at the bottom of the profile.2 In this study
a 60 cm core sample was collected in January 2013 and sliced at every 2.5 cm. The sediment samples were
dried at 40°C, ground in an agate mortar, sieved and again homogenized. The quantification of the REE
elements in sediment and pore water of each slice of the profile was performed by ICP-MS technique.
Instrumental neutron activation analysis was also applied to the sediment samples in order to determine the
total concentration for some rare earth elements (Ce, Eu, La, Lu, Nd, Sm, Tb and Yb). The validation of the
analytical methodology was performed by certified reference material analysis. The results obtained were
compared to NASC (North American Shale Composite) reference values. The distribution pattern of light
and heavy REEs in relation to condrite normalization was also verified. Furthermore, the data of this study
can be used to develop a sediment REE concentration data bank in water supply reservoirs and to establish
CETESB legal limits for REEs.
REFERENCES
1) J. Ivanova et al. Talanta 54 (2001) 567-574.
2) CETESB, 2009. Relatório de Qualidade das Águas Interiores do Estado De São Paulo 2009 – CETESB. São Paulo
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CHARACTERIZATION OF COMMERCIAL WHITE CLAYS
Giovanni Del Sordo FILHO1, Sônia Maria Barros de Oliveira2, Marcos A. Scapin1, Paulo S.
Cardoso da SILVA1
Energy and Nuclear Research Institute (Instituto de Pesquisas Energéticas e Nucleares), 2Institute of Geosciences, University of
São Paulo, São Paulo, Brazil, [email protected]
1
The first industrial use of kaolinite was the manufacture of ceramic and porcelain. Only from the 1920s it has
begun being applied in the paper industry, being preceded by the use of rubber industry. Since then kaolinite
has come to be used in plastics, pesticides, animal feed, food and pharmaceutical products, fertilizers and
others, and has currently a very wide range of industrial applications. Recently these materials have also
been studied for the adsorption of heavy metals and consequent waste industrial treatment mainly due to is
low cost.
According the DMPN (National Department of Mineral Products) the Brazilian reserves of kaolinite
reaches up to 4 billion of tons being the states of Amazonas, Pará and Amapá the major producers of this
clay mineral, followed by São Paulo, Goiais, Santa Catarina e Paraná states. Due to its color, kaolinite is
generally sold as “white clay”. Nevertheless, not all white clays are kaolinite in fact.
In this study three white clays commercially available, named CA, CB and CC were analyzed by x-ray
diffraction, x-ray florescence, neutron activation analysis and gamma spectrometry in order to verify its
composition, chemical and radiological characteristics. Also their ionic exchange capacity, percent of
moisture, organic matter and loss on ignition were determined.
Although some common characteristics had had been observed among the samples it was verified that only
one of the commercial kaolinite were in fact composed by this clay mineral.
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PROVENANCE STUDIES IN AMAZON BASIN BY MEANS OF ELEMENTAL
CHEMISTRY COMPOSITION OBTAINED BY INAA
José Osman dos Santos1, Casimiro Sepulveda MUNITA2, Emílio Alberto Amaral Soares3
Instituto Federal de Educação, Ciência e Tecnologia de Sergipe (IFS), 2Instituto de Pesquisas Energéticas e Nucleares (IPEN–
CNEN/SP), 3Universidade Federal do Amazonas, (UFAM), Aracaju, Brazil, [email protected]
1
The geological history of the Solimões-Amazon river system are recorded in the fluvial terraces at region
of confluence of the Negro and Solimões rivers. The changes in the landscape of the Amazon region it can
be observed by analyzing the sedimentary deposits quaternary in Amazon fluvial system. This study has the
purpose of contributes to determine the contribution of the sediments deposited by the Solimões and Negro
rivers in the filling of tectonic depressions and in the variations of degree of weathering between younger and
older units. The study was made using 24 chemical elements determined by instrumental neutron activation
analysis, INAA, from sediment samples collected at confluence of Negro and Solimões rivers, Manaus,
Amazon state, Brazil. The robust Mahalanobis distance (RD) was used to detect outliers in the samples. The
location and spread parameters for determination of the RDs were estimated through a subset of data. In 75%
of the total samples for each compositional group, had minimum covariance determinant The results were
interpreted using cluster and linear discriminant analysis. According to cluster and discriminant analysis,
one can infer that samples from the basin of the Solimões River and Paraná do Ariaú grabens (GPA) are
not significantly different. However, there are a clear separation of sediments from Negro and GPA groups.
It was also obtained that samples from highest and lowest terraces of the Solimões river and Paraná do
Ariaú are different, suggesting that it is a process that reflects the influence of chemical weathering on the
uppermost terrace deposits. The study provides additional subsidies to build the geological evolution of the
area.
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TRACKING IMPACTS ON CHEMICAL ELEMENT DISTRIBUTION IN DEEP
SEDIMENT PROFILES FROM A RURAL AREA OF THE PIRACICABA RIVER BASIN
Elvis Joacir de FRANÇA1, Elisabete A. De Nadai Fernandes2, Andrius Marcel Joventino do
Carmo1, Vanessa S. Rodrigues1, Emerson Emiliano Gualberto de FARIAS1
Divisão de Pesquisa e Desenvolvimento, Centro Regional de Ciências Nucleares do Nordeste, Comissão Nacional de Energia
Nuclear, 2Radioisotopes Laboratory, Centro de Energia Nuclear na Agricultura, Universidade de São Paulo, São Lourenço da
Mata, Brazil, [email protected]
1
River basins are recognized as physical entities for planning and management in order to conserve water
resources as well as reverse environmental impacts. The Piracicaba River Basin is one of the major basins in
the São Paulo State (total area of 12,400 km2). A river basin is subjected to several kinds of impacts derived
from anthropogenic activities, however there is lack of studies involving sediment profiles of rural areas. In
this work, k0-INAA was applied to quantify about 24 chemical elements in three sample profiles collected
along the Marins Stream from the Piracicaba River Basin, São Paulo State, Brazil. All sampling points
were located among diverse agricultural activities such as sugarcane and pasture. Rare earth elements were
considered conservative chemical elements to evaluateanthropogenic impacts. For double-normalization
calculation, Sc from deeper layers was used as a reference.Rare earth elements were tested according their
distribution model so that no anthropogenic alterations were detected for this group of chemical elements.
Double-normalization values did not indicate abrupt changes of chemical element distribution in sediment
profiles.However, there was a tendency of As accumulation in the recent sediments (0-15 cm) from the
riverhead Marins Stream.
Key Words: INAA, Trace Elements, Steam, Environmental Impacts.
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NEUTRON ACTIVATED RUTHENIUM(II) COMPLEXES FOR USE IN
GLIOBLASTOMA THERAPY
Aline Monezi Montel1, Raquel Gouvêa dos Santos2, Elisângela de Paula Silveira-Lacerda3,
Alzir Azevedo Batista4, Wagner Gouvêa dos Santos1
Laboratório de Genética, Regional Jataí, Universidade Federal de Goiás – UFG, 2Centro Nacional de Desenvolvimento
da Tecnologia Nuclear, CDTN, 3Laboratório de Genética Molecular e Citogenética, Instituto de Ciências Biológicas,
Universidade Federal de Goiás - UFG, 4Departamento de Química, Universidade Federal de São Carlos, Belo Horizonte,
Brazil, [email protected]
1
Targeted radionuclide therapy or radiotherapy (TR) can be an alternative way to improve the toxicity and
specificity of antitumoral drugs and consists of damaging or destroying the cells through the selective
deposition of ionizing radiation from radionuclides linked to specific biomolecules. The TR has shown
great advantages over external beam radiotherapy and neutronic activation of rutheniun-based complexes
may be a good strategy for testing new compounds for treatment of cancer1. Glioblastomas (GBM) are the
most common brain tumors in adults and the most deadly primary tumours found in the brain2,3. The high
resistance of these tumors to currently used drugs has been a challenge to obtain successful treatment for
patients diagnosed with this type of tumor. Therefore, the study of novel therapeutics agents able to inhibit the
growth of these tumours is urgent needed3,4. In this work we investigated the antitumoral effect of ruthenium
complexes: [Ru(pic)(bipy)(dppb)]PF6(1), [Ru(pic)(bipy)(dp pe)]PF6(2), [Ru(pic)(bipy)(dppf)]PF6 (3) e
[Ru(pic)(bipy)(dppp)]PF6 (4) against human GBM cell lines U87 and T98 and produced two radioactive
ruthenium complex analogs from the compounds analized by using neutron activation at the TRIGA
MARK-I IPR-RI as a tool to develop a prototype for low-dose continuous internal radio-chemotherapy for
malignant GBM. Antitumoral activity was assessed by in vitro cytotoxicity assay (MTT). MRC5 human
fibroblasts were used as normal control cells. Different concentrations of non-radioactive or radioactive
compounds were used. The compounds (2) and (4) were irradiated for 8h into polyethylene flasks carried out
on the Central position of the TRIGA MARK-I IPR-R1 nuclear reactor at the Centro de Desenvolvimento
da Tecnologia Nuclear - Comissão Nacional de Energia Nuclear (CDTN-CNEN), with a thermal neutronic
flux of 4.1x1012 n.cm-2.s-1.Cytotoxicity and apoptosis assays were performed. All ruthenium complexes
tested were cytotoxic for GBM cells in a dose dependent manner with IC50 in micromolar (μM) range.
All complexes induced morphological alterations indicative of apoptosis and necrosis. The final induced
activity for ruthenium complexes (2) and (4) after neutron activation was around 1.48x103 and 1.14x103
Bq.mg-1 respectively. Ruthenium complexes tested kept their cytotoxic activities upon neutron activation.
Therefore production of radioactive ruthenium complexes may constitute a good strategy for the preparation
of innovative therapy for malignant GBM. Further studies are in development in order to evaluate the
potential use of these ruthenium complexes.
REFERENCES
1) M. Neves, A. Kling, A. Oliveira. J. Radional. Chem. 3 (2005) 266.
2) A. Hormigo, P. H. Gutin, S. Rafii, Cancer Cell. 1 (2007) 11.
3) A. Mangliola, N. Saulnier, P. De Bonis, et al., PLoS One. 3 (2013) 8.
4) M. Ferreti, C. Fabiano, M. D. Bari, et al., J Cell Mol Med. 4 (2013) 17
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4th-INCC 2014 I 4th International Nuclear Chemistry Congress
ENVIRONMENTAL QUALITY OF RIPARIAN SOILS FROM THE PIRACICABA
RIVER BASIN
Elvis Joacir de FRANÇA1, Elisabete A. De Nadai Fernandes2, Jônas Henrique Alves de Souza1,
Paulo Correia da Silva Neto1, Rebeca da Silva Cantinha1
Divisão de Pesquisa e Desenvolvimento, Centro Regional de Ciências Nucleares do Nordeste, Comissão Nacional de Energia
Nuclear, 2Radioisotopes Laboratory, Centro de Energia Nuclear na Agricultura, Universidade de São Paulo, Recife, Brazil,
[email protected]
1
Soil compartment is one of the most important compartments in terrestrial ecosystems. Due to the
anthropogenic impacts, its chemical composition could be drastically altered, mainly in riparian areas.
Soil chemical composition from riparian areas from the Piracicaba River Basin, Piracicaba Municipality,
São Paulo, Brazil, was evaluated by instrumental neutron activation analysis – INAA. Soil samples were
collected at the 0-5 cm, 5-15 cm and 15-30 cm by means of soil sampling probe made in stainless steel. After
drying and milling until particle size of 0.5 mm, soil test portions and reference materials (sample mass =
150 mg) were irradiated in a thermal flux of 10-13 cm-2 s-1 at the Nuclear Research Reactor IEA- R1, Instituto
de Pesquisas Energéticas e Nucleares, São Paulo, Brazil. Ni-Cr allow of well known chemical composition
was used for thermal flux neutron monitoring. Induced radioactivity was measured by means of hyper-pure
germanium detectors (HPGe). Chemical element mass fractions and their respective expanded analytical
uncertainties at the 95% confidence level were calculated using the in-house software Quantu. No significant
differences at the 95% confidence level were observed among the chemical elements determined in the soil
depths. Mass fractions of As, Ba, Co, Cr, Sb and Zn were above the recommended values of soil composition
for the São Paulo State according to the Companhia Ambiental do Estado de São Paulo - CETESB. Principal
component factor analysis was employed for studying chemical element source resolution, indicating a
possible relation with the proximity of potential pollution sources such as highways, past experimentation
fields and sludge treatment station.
Keywords: INAA, Anthropogenic Impacts, Chemical Element Composition
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
EVALUATION OF VEGETATION CHEMICAL ELEMENT COMPOSITION APPLIED
TO ENVIRONMENTAL MONITORING OF URBAN RIPARIAN AREAS
Elvis Joacir De FRANÇA1, Elisabete A. De Nadai Fernandes2, Evely Elen de SOUSA1, Paulo
Correia da Silva Neto1, Rebeca da Silva Cantinha1
Divisão de Pesquisa e Desenvolvimento, Centro Regional de Ciências Nucleares do Nordeste, Comissão Nacional de Energia
Nuclear, 2Radioisotopes Laboratory, Centro de Energia Nuclear na Agricultura, Universidade de São Paulo, Jaboatão dos
Guararapes, Brazil, [email protected]
1
Brazilian legislation protects riparian areas, because of importance for the conservation of water resources.
Acting as biofilters, plant species can accumulate chemical substances from soil and sediment. Moreover,
atmospheric pollution in huge urban centers can interfere in the environmental quality of these areas. This
research focused on the determination of chemical element composition of plant trees in riparian areas
situated in the Piracicaba River, State of São Paulo, Brazil. Tree leaves from middle and upper crown of the
most abundant species were collected in different seasons (winter and summer). Samples were conducted to
the laboratory for conventional preparation (washing and oven-drying) and analysis by instrumental neutron
activation (INAA). Test portions (200 mg) and the reference materials were irradiated in a thermal flux of
10-13 cm-2 s-1 at the Research Nuclear Reactor IEA- R1, Instituto de Pesquisas Energéticas e Nucleares IPEN/CNEN, São Paulo, Brazil. A Ni-Cr wire of well-known chemical composition was used as thermal
flux monitor. The induced radioactivity was measured by high-resolution gamma-ray spectrometry based
on hyper-pure germanium detection (HPGe). The mass fractions of chemical elements and their respective
expanded analytical uncertainties were calculated by Quantu software, specific for k0-INAA. Considering
both seasons, for Ca, Co, Hf, Hg, Na, Sc, Se, Th and Zn, the mass fractions were within expected range for
plants. Likewise, Ba, Br, Cs, K, Rb and Sb mass fractions were also within their respective expected ranges,
except in few cases, in which the values have surpassed the expected maximum limits. For Ce, Cr, Eu, Fe,
La, Mo, Ni, Sm, Tb and Yb, mean mass fractions were above the expected plant ranges. According to the
correlation to Sc, Ce, Eu, Fe, La, Sm, Tb and Yb mass fractions were associated to the re-suspended earth
particulate deposited on the leaf surface mainly in the winter. Anyway, riparian areas of the Piracicaba River
have been subjected to impacts on chemical element distribution from urbanization, despite its conservation
priority.
Keywords: INAA, biofilter, urbanization
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4th-INCC 2014 I 4th International Nuclear Chemistry Congress
USE OF ROBUSTS MEANS ON THE DETERMINATION OF URANIUM FISSION
INTERFERENCE FACTOR AND ANALYSIS OF CERFIEDE REFERENCE MATERIALS
Iberê Souza Ribeiro Júnior1, Frederico Antonio Genezini1, Mitiko Saiki1, Guilherme Soares
Zahn1
Instituto de Pesquisas Energéticas e Nucleares (IPEN-CNEN/SP), São Paulo, Brazil, [email protected]
1
Instrumental Neutron Activation Analysis (INAA) is established as a technique that provides results with
high accurate and precision in the determination of several element concentrations in different kinds of
matrices. However if the sample contain high U levels problems arise due to U fission product interference.
In this study, concentration of Ce, La, Nd and Sm in Certified Reference Materials (CRMs) containing U in
their composition were determined by applying the correction due to U fission products interferences and
then compared with certified values. Both these factors and the concentration values were obtained using
four statistical methods: unweight mean, σ2 - weight mean, Normalized Residual Method and the Rajeval
Test1-3.
To determine the correct concentration on the CRMs the U fission interference factor for radioisotopes
141
Ce, 143Ce, 140La, 147Nd, 153Sm were obtained experimentally and theoretically. The interference factors
were determined experimentally by the irradiation of synthetic standards with known masses of these
elements for 8 h in a specific position of the IEA-R1 nuclear research reactor. The interference factors were
determined theoretically, using nuclear parameters from the literature and the epithermal to thermal neutron
fluxes ratio determined in the same position where synthetic standards were irradiated. The obtained value
for epithermal to thermal neutron fluxes ratio was 0.01357 ± 0.00022, determined by the irradiation of flux
monitors of Au-Al alloy using cadmium ratio technique. In the determination of the U fission interference
factors and the epithermal to thermal neutron flux ratio the same statistical methods used on the CRMs
analyzes were applied. The best results for these parameters were obtained by the Rajeval method, with high
precision in the obtained results.
The CRMs analyzed in this study were irradiated together with known masses synthetic standards inside
a same device of irradiation. The results of corrected concentration values obtained applying all of the
statistical methods were satisfactory, presenting good z-score values, however the present study recommends
the value obtained by the Rajeval method based on the best values of the reduced Chi-square, together with
high precision in the obtained results.
REFERENCES
1) M. F. James, R. W. Mills, D. R. Weaver, Nuclear Instruments & Methods in Physics Research A313 (1972) 277.
2) D. MacMahon, A. Pearce, P. Harrys, Applied Radiation and Isotopes 60 (2004) 275
3) M. U. Rajput, T. D. MacMahon, Nuclear Instruments & Methods in Physics Research A312 (1992) 289.
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REFERENCE VALUES FOR ENVIRONMENTAL QUALITY EVALUATION STUDIES
USING INVERTEBRATES. 1.ESTAÇÃO ECOLÓGICA DOS CAETETUS
Marcelo da Rocha Leão de Magalhães1, Elvis Joacir de FRANÇA1, Elisabete A. De Nadai
Fernandes2, Felipe Yamada Fonseca1
Divisão de Pesquisa e Desenvolvimento, Centro Regional de Ciências Nucleares do Nordeste, Comissão Nacional de Energia
Nuclear, 2Radioisotopes Laboratory, Centro de Energia Nuclear na Agricultura, Universidade de São Paulo, Recife, Brazil,
[email protected]
1
Despite its importance for biodiversity conservation, the protected natural areas are utmost relevant
for environmental studies, since background information has been necessary to evaluate, mitigate and
compensate environmental impacts. Terrestrial invertebrates can be considered an ecological compartment
of great importance due to the wide distribution, the high biodiversity and the adaptability to environmental
conditions. However, there is a lack of background knowledge on the accumulation of chemical substances
in such organisms. This paper provides suitable reference values for chemical element accumulation in
invertebrates. For this purpose, invertebrate samples were collected near to the Estação Ecológica dos
Caetetus - Ecological Station of Caetetus - ESC, one of the few remains of Seasonal Semideciduous Forest
from the São Paulo State, Brazil. Invertebrates captured in pitfall traps were transported to the laboratory
and classified according to the order. After washing with tap water, samples were lyophilized for 48 hours,
manually homogenized in a porcelain mortar and, then, transferred to high purity polyethylene capsules
for irradiation with neutrons (flux of 10¹³ cm-2 s-1for 8 hours) at the Nuclear Research Reactor IEA-R1,
Instituto de Pesquisas Energéticas e Nucleares, IPEN - Comissão Nacional de Energia Nuclear, CNEN - SP,
The chemical element mass fractions and their respective expanded analytical uncertainties were obtained
using the software package Quantu for k0-INAA calculation. Data of 20 chemical elements (with analytical
uncertainty less than 40%) was recorded for 15 invertebrate species. As it was expected, toxic chemical
element mass fractions were lower than 1 mg/kg. Considering the high inter-species variability, Bayesian
inference was used to obtain the credibility intervals of chemical element composition at the 95% confidence
level for establishing the first reference standards for environmental studies using invertebrates.
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4th-INCC 2014 I 4th International Nuclear Chemistry Congress
ARSENIC IN INVERTEBRATE SPECIES FROM THE PIRACICABA RIVER BASIN
Marcelo da Rocha Leão de Magalhães1, Elvis Joacir de FRANÇA1, Elisabete A. De Nadai
Fernandes2, Felipe Yamada Fonseca1
Divisão de Pesquisa e Desenvolvimento, Centro Regional de Ciências Nucleares do Nordeste, Comissão Nacional de Energia
Nuclear, 2Radioisotopes Laboratory, Centro de Energia Nuclear na Agricultura, Universidade de São Paulo, Recife, Brazil,
[email protected]
1
Arsenic is a semi-metal of average crust concentration of about 1.8 mg/kg. Its toxicity can be acute
depending on the chemical form and the environmental conditions. Microorganisms can affect mobility
and bioavailability as well as plants can accumulate this chemical element. In some regions, humans can be
affected by water and food containing high levels of arsenic, resulting in disastrous health effects. However,
there is a lack of studies of arsenic accumulation in other animals, mainly terrestrial invertebrates. This
group of animals is quite abundant, diverse and, such as humans, widely distributed. The objective of this
study is to evaluate the accumulation of arsenic in invertebrates from the Piracicaba River Basin using
instrumental neutron activation analysis - INAA. Invertebrates were captured in pitfall traps, washed in tap
water and separated by species. After free-drying for 48 hours, samples were manually homogenized in a
porcelain mortar to minimize errors due to incorrect sampling. Test portions of about 50 mg were transferred
to high purity polyethylene vials to irradiate in a thermal neutron flux of 10¹³cm-2s-1for 8 hours in the Nuclear
Research Reactor IEA-R1, Instituto de Pesquisas Energéticas e Nucleares. The lowest determinable arsenic
mass fraction was 0.16 mg/kg for Acromyrmex sp., a leafcutter ant species. Nevertheless, a mean As mass
fraction of 19.6 mg/kg was accumulated in the beetle Macrodactylus pumilio, a citrus pest. Such phenomenon
could be associated to biomagnification and/or resistance to As-containing-insecticides.
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
NATURAL RADIONUCLIDES IN MANGROVE SOILS FROM THE PERNAMBUCO
STATE, BRAZIL
Jose Daniel Soares de PAIVA1, Evely Elen Sousa1, Marcelo da Rocha Leão de Magalhães1,
Emerson Emiliano Gualberto de FARIAS1, Andrius Marcel Joventino do Carmo1, Elvis Joacir de
França1
Divisão de Pesquisa e Desenvolvimento, Centro Regional de Ciências Nucleares do Nordeste, Comissão Nacional de Energia
Nuclear, Recife, Brazil, [email protected]
1
Environmental studies in estuarine areas are scarce, especially focused at mangrove soils. The conservation
of these ecosystems is of great relevance for the maintenance of aquatic fauna and flora, the support for
coastal populations, the chemical element cycling and the radionuclide fate in the environment. However,
according to the occupation of coastal areas, mangroves have been subjected to many anthropogenic effects
such as deforestation, urbanization, domestic sludge disposal, installation of nuclear reactors and other
types of industry. Natural and artificial radioactivity could be increased in much modified areas, therefore
affecting the ecosystem maintenance. The present study focus on the evaluation of the distribution of
natural radionuclides in mangrove soils with different degrees of conservation in the Pernambuco State,
Brazil. Composite soil samples were collected (mass of 200 g) at the 15 cm depth in the Chico Science
mangrove, located in the urban area of the municipality of Olinda and mangroves from Ariquindá River
in the city of Rio Formoso. Subsequently, samples were oven-dried at 60 °C and manually comminuted in
porcelain mortar. Test portions of 50 g were transferred to polyethylene vials and sealed to establish secular
equilibrium. The reference material IAEA314 Stream sediment and internal standard RadCheMTM Custom
Soil Standard from the National Intercomparison Program, Instituto de Radioproteção e Dosimetria, were
analyzed together with the samples to guarantee the quality of the analytical procedure. After 30 days,
samples and reference materials were analyzed by high resolution gamma spectrometry with a hyper-pure
germanium detector, model GC4019, Canberra, with 40% relative efficiency and
1.9 keV resolution for 1332.5 keV photo peak of 60Co. Activity concentrations and their respective analytical
uncertainties were calculated using Genie software. By applying the independent mean t test, the average
activity concentrations of 238U and 232Th were not different at the 95% confidence level for the two mangroves.
However, significative differences were found at the 95% confidence level for 40K. The highest activity
concentrations (maximum of 1,100 Bq/kg) in the Chico Science was associated to anthropic influence on
the sediments from the Beberibe-Capibaribe Estuarine Complex.
Keywords: conservation, anthropogenic effects, gamma spectrometry.
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ACCUMULATION OF TOXIC CHEMICAL ELEMENTS IN TERRESTRIAL
MOLLUSKS
Julyanne Torres Bezerra de Mélo1, Rebeca da Silva Cantinha1, Ana Maria Mendonça de
Albquerque Melo2, Marcelo da Rocha Leão de Magalhães1, Emerson Emiliano Gualberto de
FARIAS1, Alesxandro F. Nascimento1, Elvis Joacir de FRANÇA1
Divisão de Pesquisa e Desenvolvimento – DIPED, Centro Regional de Ciências Nucleares do Nordeste – CRCN/NE, Comissão
Nacional de Energia Nuclear – CNEN, 2Departamento de Biofísica e Radiobiologia, Universidade Federal de Pernambuco,
Recife, Brazil, [email protected]
1
Copper and zinc are known to be toxic for aquatic organisms. Pollution with these chemical elements
could be disastrous for ecosystems, mainly those of intrinsic water-sediment dynamics like mangroves. In
these ecosystems, mollusks are quite representative and abundant, thereby usually employed as biomonitors
of environmental contamination. Nevertheless, little information is available for terrestrial mollusks. The
objective of this work was to demonstrate the unusual Cu and Zn accumulator capability of the terrestrial
mollusk species Littoraria angulifera (Lamarck, 1822) and Melampus coffea (Linnaeus, 1758) from
seven mangrove areas situated in Rio Formoso, Itamaracá, Ipojuca and Olinda Municipalities, State of
Pernambuco, Brazil. Sampled specimens were transported to the laboratory for sample preparation consisted
of shell removal, washing, freeze-drying, milling and microwave digestion in acid mixture. Flame atomic
absorption spectrometer, model SpectrAA200 from Agilent, was applied to determine Cu and Zn in samples
and reference materials. Expanded analytical uncertainties at the 95% confidence level were calculated based
on the estimative of precision and trueness uncertainties obtained. For L. angulifera, zinc mass fractions
achieved 170 mg/kg (U = 6%) in the preserved area, 400 mg/kg (6%) in a moderate impacted mangrove
and 7.800 mg/kg (6%) in an urban mangrove. Zinc accumulation in M. coffea was 610 mg/kg (6%) in a
moderate impacted mangrove and 2.500 mg/kg (6%) in the highly impacted area (urban). Likewise, the
mean respective Cu mass fractions were 35.8 mg/kg (5%), 60.0 mg/kg (5%) and 257 mg/kg (5%) for the
same areas of L. angulifera, while, for M. coffea, results were 27.7 mg/kg (5%) for the moderate impacted
area and 61.3 mg/kg (5%) for the urban mangrove. Different patterns of bioaccumulation were noticed for
the analyzed species, in which M. coffea presented higher Zn accumulation potential in moderate impacted
mangroves, although a hyper accumulation of this chemical element has been detected for L. angulifera.
Likewise, the species L. angulifera showed high potential to accumulate Cu. Differently from aquatic
animals, mangrove terrestrial mollusks could be considered accumulators of toxic chemical elements Cu
and Zn in mangrove areas.
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MONTE CARLO ASSISTED EFFICIENCY CURVE FOR THE DETERMINATION OF
RADIONUCLIDES IN BIOLOGICAL MATERIAL
José Daniel Soares de Paiva1, Evely Elen Sousa1, Marcelo da Rocha Leão de Magalhães1,
Emerson Emiliano Gualberto de FARIAS1, Andrius Marcel Joventino do Carmo1, Elvis Joacir de
França1
Divisão de Pesquisa e Desenvolvimento, Centro Regional de Ciências Nucleares do Nordeste, Comissão Nacional de Energia
Nuclear, Recife, Brazil, [email protected]
1
The high-resolution gamma-ray spectrometry based on hyper-pure germanium detector (HPGe) has
been widely employed for the analysis of natural and artificial radionuclides in environmental matrices.
Notwithstanding, for the analysis of biological material of low activity concentration level, the improving
of the detection efficiency is sometimes demanded, mainly by increasing sample mass. For obtaining the
efficiency curve in this case, artificial radionuclide spiked internal standards become necessary, producing large
amounts of radioactive material. Taking into account the environmental consequences, there is a possibility
of using a detector crystal characterized by Monte Carlo method to avoid spiked standards. This statistical
method allows obtaining specific efficiency curve for diverse geometries and type of materials.Therefore,
this work aimed at the implementation of Monte Carlo assisted efficiency curve to determine radionuclides
in biological samples (sample mass higher than 100 g). The detection geometry was a modified Marinelli
beaker with maximum volume of 58 cm3. The efficiency curve generated by the ISOCALS software from
Canberra was based on the geometry shape constructed using the Geometry Composer software (Canberra).
The quality of this analytical procedure was investigated using the internal standard Vegetation (mass of
200 g) from the National Intercomparison Program from the Instituto de Radioproteção e Dosimetria - IRD.
This material presents activity concentrations of 40K, 60Co, 65Zn, 134Cs, 137Cs and 241Am. According to the
calculation of the En number, radionuclide activity concentrations agreed to the certified values at the 95%
confidence level with exception of 241Am (bias of about 26%). Monte Carlo assisted efficiency curve was
considered adequate for the quantification of high gamma-ray energy emission radionuclides.
Keywords: gamma-ray spectrometry, HPGe, detection geometry.
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INSTRUMENTAL NEUTRON ACTIVATION ANALYSIS TO DETERMINE THE
ANNUAL RADIATION DOSE FOR THERMOLUMINESCENCE DATING OF POTTERY
FROM CANINDÉ-SERGIPE, BRAZIL
José Osman dos Santos1, Mauro José dos Santos1, Casimiro Sepulveda Munita2
Instituto Federal de Educação, Ciência e Tecnologia de Sergipe, IFS, 2Instituto de Pesquisas Energéticas e Nucleares (IPEN–
CNEN/SP), Brazil, [email protected].
1
Thermoluminescence (TL) dating is an important method for dating archaeological potteries,
the method is based in the thermoluminescence emission of the quartz signal. The age calculation requires
estimating two factors: the equivalent dose (De) which is the absorbed dose and the annual dose (Dan). The
ratio between both doses, De / Dan, provides the age. In order to obtain pure quartz grains from each ceramic
fragment to estimate de De a chemical procedure was used. The Dan dose rate determination was performed
by means of the determination of U, Th and K concentrations using INAA. This paper shows as the relation
of thermoluminescence (TL) and radiochemistry techniques can help to solve chronological problems for
areas with poorly stratified sites and few organics remains, such as archeological sites at Canindé - Sergipe,
Brazil. This study uses TL to dating potteries that were collected during the excavation at Canindé, where
the potteries is greatly expressed because many ceramics are associated to mortuary sites. The additive dose
method was used to determine the paleodose in potteries samples in which the response at 320 ºC peak as
a function of the added dose was linear. The ages determined resulted in a range between 457 and 3,716
BP. Considering the results, this work provide a contribution for chronological reconstruction of Brazilian
Northeast ceramist population.
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SILICON IN TEN SUGARCANE VARIETIES MEASURED BY ENERGY DISPERSIVE
X-RAY FLUORESCENCE
Maria Isabel Vega Martínez1, Cláudio Luís Gonzaga1, Elisabete A. De Nadai Fernandes1,
Márcio Arruda Bacchi1, Lilian Seiko Kato1, Isabel Cristina Azevedo Schiavinato1, Eduardo
de Almeida1
Nuclear Energy Center for Agriculture (CENA), University of São Paulo (USP), Piracicaba, Brazil, [email protected]
1
Silicon (Si) is not considered an essential nutrient for most plant species, but is a common mineral component
of vegetable tissues with recognized importance for plant health, improving resistance against pest, diseases
and hydric stress. Particularly for sugarcane, the essentiality of Si has been demonstrated. According to
Meyer,[1] Si in sugarcane is important for providing a better yield response, preventing Al and Mn toxicities,
improving photosynthesis and P nutrition, amongst other benefits. Sugarcane is cultivated in more than 90
countries around the world. Brazil has been the first producer for decades, being presently responsible for
40% of the world production of sugarcane. Motivated by the clear need for higher production in the coming
years, new sugarcane varieties have been developed seeking to enhance productivity. Such new varieties
must comply with several requirements, including optimal utilization of nutrients, high sugar content, and
resistance to diseases, pests and climate conditions. The accumulation of Si in sugarcane depends on the
variety and field status, therefore the measurement of Si in leaves is relevant for the diagnosis of deficiency
and subsequent correction. On the other hand, sugarcane leaves have high fiber content with a predominance
of lignin, which combined with the high Si content hinders complete digestion of samples for chemical
analysis. Here, energy dispersive X-ray fluorescence (ED-XRF) was used for measuring Si in leaves of
sugarcane varieties produced in Brazil. Ten sugarcane fields with about 6 months age and similar soil fertility
conditions were chosen for this study. Such fields comprised ten different sugarcane varieties amongst the
most cultivated in São Paulo state. Material was collected in ten points of each field, resulting a total of 100
samples, each composed of 100 leaves. In the laboratory, each leaf was divided into three parts and only
20 cm of the intermediate portion was taken for analysis, after removing the midrib. Samples were dried in
oven at 50ºC during three days. Each dried sample, with about 40 g, was preliminarily processed in a knife
mill and then finished in a rotor mill using a stainless steel sieve of 80 μm to further reduce the particle size.
Analytical portions of 500 mg were weighed in triplicate and pressed in X-Press applying 15 t/cm2 during
5 min. The pellets obtained were approximately 2 mm thick with 15 mm diameter. The Si concentration
in leaves was measured using the characteristic X-ray radiation emitted (kα 1.74 keV) and detected using
a Shimadzu 720 ED-XRF equipment. Compared to literature values,2 results demonstrated three varieties
with deficient levels of Si, less than 0.50 % (SP832847, CTC17 and CTC15), four varieties with adequate
levels, between 0.51 % and 0.75% (CTC2, IACSP955000, CTC4 and RB966928), and three varieties with
high levels, more than 0,75 % (CTC14, CTC20 and CTC11).
REFERENCES
1) J. H. Meyer, M. G. Keeping, Proc. S. Afr. Sug. Technol. Ass. 74 (2000) 29-40.
2) L. L. Dinardo-Miranda, V. A.C. Machado, M. Guimarães, Cana-de-açúcar. Campinas, 2010, 882p.
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Chemical characterization of brazilian beans using neutron
activation analysis
Lilian Seiko Kato1, Elisabete A. De Nadai Fernandes1, Márcio Arruda Bacchi1, Gabriel Adrián
Sarriés2
Nuclear Energy Center for Agriculture, University of São Paulo (CENA/USP), 2College of Agriculture “Luiz de Queiroz”,
University of São Paulo (ESALQ/USP) , Piracicaba, Brazil, [email protected]
1
Beans are of global importance, especially in the Americas, which accounts for 43% of the world
consumption. Brazil, besides being the third largest producer amongst 124 countries growing beans,1 has a
large consumption as a staple food combined with rice. Beans are considered an important source of proteins,
carbohydrates and iron. Here, a comprehensive study was carried out for characterizing beans available
in Brazil, providing information about chemical composition to compare the different commercial types.
Fifty-three samples of beans were acquired directly in the consumer market of Piracicaba, SP, covering nine
commercial types of the species Phaseolus vulgaris and one of the species Vigna unguiculata. Samples of
different commercial brands originated from four states of Brazil, i.e. Minas Gerais, Paraná, Santa Catarina
and São Paulo. A portion of 250 g from each sample was oven dried at 50°C for 24 h and subsequently
processed in a knife mill (Retsch Grindomix GM 200) for reducing the particle size. Replicated analytical
portions of 400 mg from each powdered sample were directly weighed into high purity polyethylene
capsules for instrumental neutron activation analysis (INAA). The analytical series also included certified
reference materials for quality control, empty capsules for blank evaluation and NiCr wires for neutron
flux monitoring. Irradiation was carried out in the nuclear research reactor IEA-R1 of IPEN/CNEN, with
a neutron flux of 9x1012 cm-2 s-1 for 4 h, and the induced radioactivity was measured at CENA/USP, using
high-resolution gamma-ray spectrometry. Eleven chemical elements (Br, Ca, Co, Cs, Fe, K, Mo, Na, Rb,
Sc and Zn) could be determined in the beans, six of them (Ca, Fe, K, Mo, Na and Zn) considered essential
to humans at different levels. For comparison of the different commercial types, the statistical analysis
involved the application of the Gauss-Markov Model in ANOVA, Tukey’s test, MANOVA, Student’s T test,
Cluster Analysis (CA) and Principal Components Analysis (PCA). There was large variability within each
commercial type for trace elements, while small variation occurred for nutritional elements. No significant
difference was observed amongst the commercial types of beans for Br, Rb and Sc (p<0.05). Nevertheless,
significant differences were observed for Ca, Co, Fe, K, Mo, Na and Zn (p<0.05). The commercial type
Fradinho (Vigna unguiculata) differed from all other types, presenting the lowest concentrations of Ca, Co
and K, and the highest concentrations of Na and Cs.
REFERENCES
1) FOOD AND AGRICULTURE ORGANIZATION STATISTICAL DATABASE (FAOSTAT). http://faostat.fao.org.
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HEAVY METALS MEASUREMENT IN SANDY BEACHES: INFLUENCE OF THE
BENTHIC FAUNA ASSOCIATED
Rodholfo Maciel de Mendonça Ribeiro1, Leonardo Q. Yokoyama1, Renata F. Barbosa1,
Edgar Francisco Oliveira de Jesus2, Roberta de Oliveira Resende Ribeiro3, Roseli Fernandes
Gennari4
Department of Marine Sciences - UNIFESP, 2Nuclear Instrumentation Laboratory - UFRJ, 3Laboratory of Chemical Control UFF, 4Physics Institute, Sao Paulo University - USP, Santos, Brazil, [email protected]
1
Heavy metals in trace amounts are naturally found in the environment some of them are essentials to life,
however, they cause toxicity at high concentrations1. The absorption of heavy metals on intertidal sandy
beaches sediment is related to the contamination of its inherent biota2. It may affect not only on the metal
concentration on body tissues but also on the diversity and distribution of these organisms. The scientific
literature did not present results that consider the influence of benthic fauna at concentrations of trace metals
in the sediment. Based on the literature about heavy metals contamination at sediment from sandy beaches,
this work aims to analyze the influence of the benthic fauna (macro- and meiofauna) in the quantification of
trace metal contents of sandy beaches. Sediment from the intertidal regions of Itararé, Boracéia and Guaecá
beaches, located along the São Paulo State coast (southeast Brazil), will be sampled and analysed for heavy
metal contents and granulometric composition. This region’s sediment grains must be morphologically
similar so they can be compared for this aim were made organic material tests and granulometry tests. The
collected sediment will get through differents processes for comparison: the first will not be processed, the
second one will be sieved to macrofauna’s separation and the third one will use LUDOL for the macrofauna
& meiofauna is lifting. Macrofauna will be sorted out by sieving the sediment through a 0.5 mm mesh, while
the meiofauna will be removed from the sediment by a flotation technique. Heavy metals concentrations will
be analyzed using TXRF and ICP techniques.
REFERENCES
1) G. W. BryanProc. R. Soc. Lond 177 (1971) 389-410
2) A. Cesar, C. D. S. Pereira, A. R. Santos, D. M. D. S. Abessa, N. Fernández, R. B. Choueri, and T. A. Delvalls, Braz. J.
Oceanogr. 54 (2006) 55-63.
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CONTRIBUTION TO FOOD SAFETY ASSURANCE OF THE FISH CONSUMED IN SÃO
PAULO CITY: THE DETERMINATION OF ELEMENTS BY NEUTRON ACTIVATION
ANALYSIS
Karen Campos Fabiano1, Edson Gonçalves MOREIRA1, Marina BeatrizAgostini Vasconcellos1
Instituto de Pesquisas Energéticas e Nucleares, IPEN – CNEN/SP, São Paulo, Brazil, [email protected]
1
Fish is considered a nutritious food as it is a source of protein, polyunsaturated fatty acids, vitamins and
minerals. For this reason fish consumption has increased in Brazil in recent years, also raising the fish
quality control by Brazilian health authorities, with constant concern over the presence of contaminants.
In general, the occurrence of many potentially toxic inorganic and organic compounds is related to water
contamination and environment pollution which can result in abnormal levels, considered above the limits
for human consumption. Within this context, the Neutron Activation Laboratory of IPEN - CNEN/SP
participated in a technical cooperation project of the International Atomic Energy Agency directed to Latin
America countries (IAEA ARCAL CIII) aiming the assurance of food quality and monitoring contaminants
in shellfish and fish.
In this study the concentrations of elements present in the some of the most consumed species in São
Paulo City were determined by Instrumental Neutron Activation analysis (INAA) and Atomic Absorption
Spectromety (AAS). Subsequently, obtained values were compared to the limits of existing legislations,
national and international, which set the maximum permitted concentration of elements in foods. The
species analyzed were whitemouth croaker (Micropogonias furnieri), sea bass (Centropomus sp.), hake
(Cynoscion leiarchus) and sardines (Sardinella brasiliensis). The elements analyzed were As, Br, Cd, Co,
Cs, Fe, Hg, K, Na, Pb, Rb, Se and Zn. Ten specimens of each fish were purchased from Companhia de
Entrepostos e Armazéns Gerais de São Paulo (CEAGESP), main supply center for the population of the
metropolitan area of São Paulo. After gutted and cleaned, the edible tissues were freeze-dried, ground, sieved
and homogenized. Element determination was performed with use of hiperpure germanium spectrometer
after irradiation at the IEA-R1 nuclear research reactor. With the exception of seabass, the other species had
As concentrations above those permitted by the Brazilian legislation (1.0 mg kg-1)1.
REFERENCES
1) BRASIL. Ministério da Saúde, Secretaria de Vigilância Sanitária, Portaria no 685, de 27 de agosto de 1988, Fixa limites
máximos de tolerância de contaminantes químicos em alimentos, Diário Oficial da República Federativa do Brasil, Brasília,
24 de setembro de 1998, Seção 1, Parte 1, p. 1414-1437, 1998.
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TRACE ELEMENTS DETERMINATION IN LEAVES OF NERIUM OLEANDER USING
X-RAY FLUORESCENCE
Ramon Silva dos Santos1, Francis Anna Cardoso Reis de Almeida Sanches1, Arthur O. P.
Neves1, Davi Ferreira de Oliveira1, Luis Fernando de Oliveira1, Marcelino José dos Anjos1
Physics Institute, State University of Rio de Janeiro, Rio de Janeiro, Brazil, [email protected]
1
The quality of the air is a topic of great importance worldwide as it affects the human health, animals and
plants. The air pollutants continuously enter in the human body, causing illness as skin problems, asthma,
bronchitis, pulmonary diseases and eyes irritation. With the cities fast growth and the industrialization process
the air pollution was aggravated due to different types of emissions associated with these processes, as urban
traffic, industrial activities, burning fuel, civil industries of construction/demolition, fires and also natural
phenomena. Many of these emissions move from long distances due to convections currents and finally tend
to deposit mainly in the plants leaves and in the soil, so it can influence the function and the structure of the
ecosystem, including its ability of self regulation, thus affecting its life quality. Therewith, plants leaves can
behave as a natural sample of the emissions that are deposited in the same. In this study Nerium oleander
leaves were used to measure the environmental pollution levels in different sampling urban regions in the
city of Rio de Janeiro/RJ: Andaraí, Benfica, Bonsucesso, Caju, Engenho de Dentro, Engenho Novo, Estácio,
Grajaú, Inhaúma, Lins, Maracanã, Maria da Graça, Méier, Praça da Bandeira, Riachuelo, Rio Comprido,
São Cristóvão, Tijuca, Vila Isabel and city Center. The control samples were collected in Campo Grande
near of Parque Nacional da Pedra Branca/RJ (National Park of Pedra Branca/RJ). The leaves were collected
from adult plants and after the collection the samples were cleaned and placed in the greenhouse for drying,
then were mashed and pressed into tablets forms. The analyses were performed using the energy dispersion
X-ray fluorescence (EDXRF), developed on the own laboratory and based in a SiPIN detector and a mini
X-ray tube. It was possible to detect 12 elements in the analyzed samples: K, Ca, Cr, Mn, Fe, Cu, Zn, Br,
Rb, Sr, Ba and Pb. The results show that all elements present higher concentrations than those found in the
control samples. Indicating that the biggest source of pollution in these areas has anthropogenic origins as
fossil fuel burning in internal combustion engines of motor vehicles, industry and activities associated to
the civil construction.
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ANALYSIS OF TRACE ELEMENT IN RIVER WATER SURFACE USING A PORTABLE
TOTAL REFLECTION X-RAY FLUORESCENCE SYSTEM
Ana Cristina Moraes da Costa1, Ubiratan Barbosa de Araújo1, Edgar Francisco Oliveira de
Jesus1, Marcelino José dos Anjos1-2, Ricardo Tadeu Lopes1
Nuclear Instrumentation Laboratory – COPPE/UFRJ, 2State University of Rio de Janeiro, Physics Institute, Rio de Janeiro,
Brazil, [email protected]
1
This paper presents a portable total reflection X-ray fluorescence system (TXRF) composed of a 15 W
X-ray tube, with a gold anode, a waveguide constituted by two Perspex® parallel plates, a SiPIN detector
and a quartz optical flat. The critical angle of the total reflection system was experimentally determined
by measuring a zinc solution (100 mgL-1). The accuracy of the system was checked using SRM 1577b
Bovine Liver by NIST as standard reference material. We obtained the detection limits of the following
elements: P (30±3 mgg-1), S (13±2 mgg-1), K (2.5±0.2 mgg-1), Ca (1.0±0.2 mgg- 1), Mn (0.300±0.040 mgg-1),
Fe (0.220±0.060 mgg-1), Cu (0.222±0.030 mgg-1) and Zn (0.225±0.020 mgg-1). Subsequently, an application
in the environmental field from the analysis of surface water samples from rivers in the Pedra Branca State
Park (Rio de Janeiro, Brazil) was performed. The results obtained from the analysis of the rivers water
were compared with the results obtained in the X-ray Fluorescence line of the Brazilian Synchrotron Light
Laboratory. The TXRF system showed to be very efficient in multielemental analysis for the determination
of trace elements in samples of surface water from two rivers (dissolved phase): S, K, Ca, Fe, Cu and Zn.
So, this paper shows that it is possible to produce total reflection X-ray fluorescence with a very compact,
efficient, low-cost and easy-to-handle instrumentation using a low-power X-ray tube and a Si PIN compact
detector.
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RARE EARTH ELEMENTS: PAST, PRESENT AND FUTURE AT RADIOISOTOPES
LABORATORY
Luís Gustavo Cofani dos Santos1, Elisabete A. De Nadai Fernandes1, Simone Silveira Nery da
Silva Cofani dos Santos1, Márcio Arruda Bacchi1, Gabriel Adrián Sarriés2, Mateus Eugênio
Boscaro1
Centro de Energia Nuclear na Agricultura, Universidade de São Paulo, 2Escola Superior de Agricultura Luiz de Queiroz,
Universidade de São Paulo, Piracicaba, Brazil, [email protected]
1
The International Union of Pure and Applied Chemistry classifies as rare earth elements (REEs) the group
of chemical elements corresponding to lanthanides (La, Ce, Pr, Nd, Pm, Sm, Eu, Gd, Tb, Dy, Ho, Er, Tm,
Yb e Lu) plus scandium (Sc) and yttrium (Y). Due to their similar chemical and physical properties, the
REEs form a cohesive chemical group divided into two categories, light REEs and heavy REEs. Despite the
name, REEs constitute about 18 % of all elements on Earth and occur in a wide range of minerals including
carbonates, phosphates and silicates. Around 200 minerals are known to contain REEs however only a
small number of these are or will become commercially exploitable. Brazil was a pioneer in exploration
and production of REEs, but since 1990 the commerce suffered significant setbacks due to the expansion of
international production. In accordance with recent Brazilian document the resumption of the exploration
of REEs is a national challenge. It is necessary to have access to the national raw material and invest in
technology to build up an environmentally friendly and socially just productive chain. In this sense, it
is primordial that the safety conditions of work are followed, and additionally the sources of air, food
and water accessible to workers and population are also protected from contamination by chemicals, toxic
elements and radiation. Therefore, it is concluded that the creation of centers of analytical support focused
on productive chain of REEs is of fundamental importance. Chemical analyses of high metrological level
to quantify REEs are essential to knowing in detail the potential exploitation of Brazilian reserves. In the
past, the Radioisotopes Laboratory (LRi) at Nuclear Energy Center for Agriculture (CENA), University
of São Paulo (USP), had shown expertise in the determination of REEs in food samples, arboreal species
of Atlantic forest, sediments of Amazon basin and continental platform, uranium mining waste rocks and
phosphate tailings from Catalão. At present, there is an ongoing project fomented by the Coordination for
the Improvement of Higher Education Personnel (CAPES) with the main objective of chemically evaluating
different reserves, byproducts and mineral rejects that contain REEs in their composition by using neutron
activation analysis. For this work, low energy gamma-ray spectrometry is being implemented especially to
determine Er, Ho and Tm. All the activities associated at promoting sustainability of national production
chain of REEs and training of human resources in this strategic sector for the country will be thoroughly
presented and discussed.
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CHEMICAL CHARACTERIZATION OF MILK POWDER FOR THE PRODUCTION OF
CERTIFIED REFERENCE MATERIAL
Simone Silveira Nery da Silva Cofani dos Santos1, Elisabete A. De Nadai Fernandes1, Luís
Gustavo Cofani dos Santos1, Márcio Arruda Bacchi1, Gabriel Adrián Sarriés2
Centro de Energia Nuclear na Agricultura, Universidade de São Paulo, 2Escola Superior de Agricultura Luiz de Queiroz,
Universidade de São Paulo, Piracicaba Piracicaba, Brazil, [email protected]
1
Milk is a dispersion rich in calcium and many other important nutrients to human health. Due to nutritional
properties, Food and Agriculture Organization (FAO) indicates the dairy sector as strategic to reducing
world hunger. Since 2008, Brazil is the fourth largest producer of fresh milk from dairy cattle. The milk
sector has some particularities in the domestic market. There are big differences between managements of
livestock, from cattle grazing to total confinement. The main producers are distributed in various states of
the country. In 2012, the production of fresh milk of dairy cattle was the fifth most important commodity
of the country, also from an economical standpoint. Hundreds of millions of tons of milk are processed
annually to produce milk powder by dehydrating whole, partially skimmed or skimmed cow´s milk through
technologically appropriate processes. Because of stability and easy transportation, milk powder is widely
used for manufacturing dairy related food. However, to meet the growing concerns about the quality
and fulfill international requirements, the Ministry of Agriculture, Livestock and Food Supply (MAPA)
approved the Normative Instruction 51 (IN51) within the National Programme for Improving Milk Quality
(PNMQL). This law required the analysis of milk quality for industries and producers. In this context, the
Brazilian Laboratory Network of Milk Quality Analysis (RBQL) was created. On the other hand, chemical
measurements in food aim at assessing its composition and check its quality and safety. Observing the
maximum possible chemical residues in milk, IN51 refers to the National Residue Control Plan (PNCR) of
MAPA. The community of analytical chemists requires principles of quality assurance for their analyses.
Performing reliable chemical analysis is not a simple task, since the measurement procedure may depend on
sample matrix, leading in many circumstances to separate analyte from sample matrix. In this context, certified
reference materials (CRMs) provide the means to validate, check and calibrate measurement procedures
and instrumentation, reducing losses caused by incorrect analytical results and allowing verification of
accuracy of measurements. MAPA expressed strong demand for certified reference materials of animal
and plant matrices, in particular milk powder, by promoting actions to achieve sufficiency in technological
development. The Radioisotopes Laboratory gained expertise in chemical analysis of milk and production
of matrix certified reference materials (CRMs). Thus, this master degree research, promoted by National
Council for Scientific and Technological Development (CNPq), intended to chemical characterization of
different types and brands of milk powder available in the market by means of neutron activation analysis
and inductively coupled plasma mass spectrometry. The results will allow the selection of candidates for
future production of certified reference materials of this important food matrix.
i
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STUDIES ON RARE EARTHS IN URANIUM MINING WASTE ROCKS USING
NEUTRON ACTIVATION ANALYSIS
Elisabete A. De Nadai Fernandes1, Márcio Arruda Bacchi1, Gabriel Adrián Sarriés2, Luís
Gustavo Cofani dos Santos1, Mateus Eugenio Boscaro1, Luiza Oide Wiikmann1, Peter Bode3
Centro de Energia Nuclear na Agricultura (CENA), Universidade de São Paulo (USP), 2Escola Superior de Agricultura Luiz
de Queiroz (ESALQ), Universidade de São Paulo (USP), 3Radiation Science and Technology, Delft University of Technology
(TUDelft), Piracicaba, Brazil, [email protected]
1
The consumption of rare earth elements has nearly tripled in the last decade and the trend is to increase
further. Research and development activities have contributed to this expansion and opened a large number
of markets, such as permanent magnets, wind turbines, electric and hybrid cars, video devices, clinical
diagnostics, among others. In other words, the rare earth elements and compounds are strategic for industrial
and technological innovations in the 21st century. Brazil has pioneered the exploration and production of rare
earths from monazite in the second half of the 1940s, becoming the largest industrial producer worldwide.
From 1990, China took the lead and produces today about 97% of rare earths consumed in the world. China
has restricted drastically and unexpectedly sales of its rare earths in 2011, thereby many countries have
found themselves again interested in mapping and exploit their own reserves of rare earths. According to
USGS, Brazil has one of the largest geological reserves in the world, which can be substantially higher
when considering the REEs associated to several ores possibly recovered as a byproduct. In this context,
the uranium mining activities at Poços de Caldas plateau performed between 1977 and 1995 generated huge
amounts of waste rocks which were dumped into piles around the mine pit. In this work, a comprehensive
sampling of these waste rocks allowed to study their rare earth element contents by instrumental neutron
activation analysis (INAA) using normal (about 200 mg) and large (about 2 kg) samples. The results
permitted to conclude that the rare earth elements were enriched in relation to earth crust, mainly the lighter
elements La, Ce, Nd and Sm. Also, it was demonstrated that the waste rocks are extremely heterogeneous
requiring even larger quantities of sample for reliable chemical characterization.
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OBTAINING OF THE NUCLEAR GRADE ZIRCONIUM TETRACHLORIDE BY THE
CHLORINATION PROCESS
Rubens Chiba1, Eliene G. R. Menezes1, Marco Andreoli1, Emília Satoshi Miyamaru Seo1
IPEN - Instituto de Pesquisas Energéticas e Nucleares, São Paulo, Brazil, [email protected]
1
The nuclear grade tetrachloride zirconium (ZrCl4) is an important chemical reagent for obtaining of the
metallic zirconium sponge. The metallic zirconium with other alloy elements is one of the main inputs for
the manufacture of the fuel rods of the fuel element, used in nuclear reactors. The raw material zirconium
oxide (ZrO2) for obtaining of the zirconium tetrachloride is formed in porous pellets. The pellets are obtained
in the pelletizing process1, which consists in adding the powder mixture composed of zirconium oxide,
graphite and sugar that are added to the plate pelletizer equipment. The forming in porous pellets is required
for a better packing in the alumina reactor and good chemical reaction kinetics in the chlorination process2.
The chlorination process consists in chemically react the zirconium oxide pellets with chlorine gas to obtain
zirconium tetrachloride. The ZrO2 pellets are fed into the alumina reactor located inside of the chlorination
furnace, which reacts with the chlorine gas, condensing to form the ZrCl4. The operation temperature of
the chlorination furnace is controlled by a supervisory panel. The objective of this work is to present the
development of the chlorination process directing for obtaining of the nuclear grade zirconium tetrachloride.
The raw materials such as porous pellets were characterized by X-ray diffractometry (XRD), scanning
electron microscopy (SEM), porosity, compression test and drop test, aiming microstructural and physical
characteristics suitable for the process. And the ZrCl4 product was characterized by inductively coupled
plasma optical emission spectrometry (ICP-OES) for verification of the impurities contained in the product.
The study to the chlorination process of the ZrO2 pellets allowed the obtaining of the ZrCl4 in favorable
conditions for production of this material in laboratory scale, aiming for obtaining of the zirconium sponge
by the reduction process.
REFERENCES
1) E. G. R. Menezes, M. Andreoli, R. Chiba, E. S. M. Seo, Anais do 57° CBC (2013).
2) E. S. M. Seo, A. Abrão, Série Publicação IPEN 116 (1987).
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DEEP-SEA MICROSPHERULES FROM THE PACIFIC AND THE INDIAN OCEANS:
ELEMENTAL COMPOSITION AND POSSIBLE ORIGIN
Zdeněk Řanda1, Jiří Mizera1
Nuclear Physics Institute, Academy of Sciences of the Czech Republic, Řez, Czech Republic, [email protected]
1
Microspherules, or bodies of similar shape sized usually under 1 mm, occur on land as well as at the bottom
of oceans and in glaciers. Ideal reservoirs for their sampling are namely glaciers and fine deep-sea sediments
far from the mainland, thanks to very low sedimentation rate (1 mm per 1000 years) of fine, μm-sized,
particularly clay particles. These microspherules vary widely in composition and they are of both natural and
anthropogenic origin. Their natural production includes ablation of cosmic dust and meteoroids, volcanic
activity, impacts of large cosmic bodies (microtektites), or extensive wildfires. The anthropogenic sources
include coal combustion, metallurgic processes, welding and machining of metals, nuclear weapons test,
and space exploration (burning solid fuels in rockets, satellite termination by burning in the atmosphere).
In the course of the oceanographic expeditions in the Pacific Ocean aimed at investigation of Fe-Mn
nodules (in 1978 and 1979, sampling region 8° N, 154° W and 13° N, 138° W) and Indian Ocean (in
1983, sampling region 13° S, 77° E), also red clay samples were collected from a 5000-m depth using both
grab and core sampling. From the fine clay samples (approximately 1 ton from each sampling region),
a coarse, heavy fraction containing microspherules was separated by a sink-float procedure for further
processing in laboratory. In the Indian Ocean samples, where the presence of microtektites associated with
the Australasian tektite strewn field was expected, besides magnetic microspherules also non-magnetic,
vitreous microspherules were separated from heavy liquids and under the microscope. In the Pacific Ocean
samples, where the microtektite presence was improbable, only magnetic microspherules were separated.
For geochemical analysis of the microspherule samples, INAA was employed, both in the short-time
irradiation mode mainly for determination of major elements, and in the long-time irradiation mode for
determination of trace element. Polished sections were prepared from selected samples and analyzed by
electron microprobe.
Several tens of magnetic iron microspherules from the Pacific Ocean were divided into three groups
according to colour - brown-black, black dull, and black lustrous. High contents of Fe, Ni, Co, Cr, and
particularly Ir (0.5-1.2 ppm) indicated their extraterrestrial origin. Composition of virtually all of sixty-eight
magnetic microspherules from the Indian Ocean pointed to their anthropogenic origin (Ti content up to 25
wt%, high levels of Mg, Ta, etc.), among others probably from burned parts of rockets or satellites. None of
five vitreous microspherules separated from the samples from this region corresponded by composition to
the composition of the Australasian tektites, and these siliceous glasses with high Ca content were with little
doubt of anthropogenic origin.
The study was supported by the project 13-22351S of the Czech Science Foundation.
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MONITORING OF 226Ra, 228Ra, 210Pb AND 210Po IN THE COASTAL REGION OF SÃO
PAULO STATE, BRAZIL, USING OYSTER Crassostrea brasiliana
Gabriela de Jesus Lustoza Costa1, Cátia Heloisa Rosignoli Saueia1, Barbara P. Mazzilli1,
Marilia Gabriela Miranda Catharino Semmler1, Eduinetty Ceci Pereira Moreira de Sousa2
Instituto de Pesquisas Energéticas e Nucleares (IPEN), 2Instituto Oceanográfico da Universidade de São Paulo (IO-USP),
São Bernardo do Campo, Brazil, [email protected]
1
The present study aims to identify and to determine the radionuclides 226Ra, 210Pb, 210Po and 228Ra in oyster
Crassostrea brasiliana. This organism is used as bioindicator, since it accumulate in its tissues, chemical
contaminants present in its natural habitat. The bivalves samples were seasonally collected in three sites
of São Paulo State coast, from September of 2008 to July of 2009, as follows: Cananéia estuary, Bertioga
and Canal de Santos – Santos estuary (impacted by industrial and human activities). The samples were
digested using a microwave digestion system, after adding concentrated HNO3 and H2O2. The 226Ra and
228
Ra concentrations were determined by measuring the gross alpha and beta activity of the precipitate
Ba(Ra)SO4 after 21 days and the concentration of 210Pb was determined through its decay product 210Bi, by
measuring the gross beta activity of the precipitate of 210PbCrO4. Both radionuclides were measured in a low
background gas flow proportional detector. 210Po was determined by spontaneous deposition on a silver disc
and measurement by alpha spectrometry. The concentration of 226Ra varied from 5.3 ± 1.0 Bq kg-1 to 18.6
± 3.4 Bq kg-1; for 210Pb from 2.7 ± 0.1 Bq kg-1 to 44.9 ± 2.3 Bq kg-1; and for 210Po from 5.1 ± 1.0 Bq kg-1 to
20.5 ± 0.4 Bq kg-1. For the radionuclide 228 Ra, the values were below the minimum detectable activity of
the methodology (0.04 Bq kg-1). No correlation was observed between the concentration of 226Ra, 210Pb and
210
Po and the seasons.
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NITROGEN ASSAY BY INSTRUMENTAL PHOTON ACTIVATION ANALYSIS WITH
THE MT-25 MICROTRON
Ivana Krausová1, Jiří Mizera1, Zdeněk Řanda1, Pavel Dostálek2, Jan Táborský3,
Marcela Mádlíková1-3, Oldřich Faměra3, David Chvátil1, Pavel Krist1
Nuclear Physics Institute, Academy of Sciences of the Czech Republic, 2Institute of Chemical Technology Prague, 3Czech
University of Life Sciences Prague, Řez, Czech Republic, [email protected]
1
Instrumental photon activation analysis (IPAA) is a useful and complementary method to instrumental
neutron activation analysis (INAA). IPAA allows determination of several elements not determinable by
INAA, and determination of other elements with better sensitivity than INAA. IPAA is based on photonuclear
reactions induced by photon radiation with sufficiently high energy to exceed the reaction threshold. The
threshold energies exceed 10 MeV in the case of the photodisintegration reactions (γ, n), which have the
greatest analytical potential for IPAA. An effective source of such high energy (up to 25 MeV) photon
radiation is the MT-25 microtron, where suitable radiation is produced as bremsstrahlung by deceleration of
accelerated electrons on a water-cooled tungsten target.
The study presents an IPAA procedure for assaying nitrogen in biological and other materials. The
determination has been based on counting of the non-specific 511 keV annihilation gamma rays of 13N,
a short-lived (half-life 9.97 min) product of the photonuclear reaction 14N(γ, n)13N with the threshold
energy 10.6 MeV. Since 13N is a pure positron emitter, its determination can be interfered by simultaneous
formation of several other positron emitters. Formation of 15O can be eliminated thanks to considerably
higher threshold energy and shorter half-life than those of 13N (15.7 MeV and 2.04 min, respectively) by
optimizing the beam energy and decay time (17 MeV and 15-20 min, respectively). The interferences from
34m
Cl and 38K can be corrected by evaluation of their contribution to the 511 keV line using their other
specific gamma lines measured in correction standards for these elements. The IPAA procedure was tested
and optimized by analysis of selected biological reference materials - NIST RM 8433 Corn Bran, 1547
Peach Leaves, 8414 Bovine Muscle, and 1577b Bovine Liver. The optimized procedure was applied to
assaying nitrogen in biological materials as malting barley and winter wheat with LOD down to 1 wt%, and
in other materials as synthetic diamonds and nanodiamonds designed for medical applications, with LOD
down to 0.01 – 0.02 wt%.
The work has been supported by the projects 13-27885S and P108/12/G108 of the Czech Science Foundation.
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URANIUM ISOTOPIC RATIO DETERMINATION BY ICP-MS
Luís Cláudio de OLiveira1, Israel Elias Ferraz1, Talita Sousa1, Ricardo Gonçalves Gomide1,
Ieda de Souza Silva1
CTMSP – Centro Tecnológico da Marinha em São. Iperó/SP, Sorocaba, Brazil, [email protected]
1
The analysis of the isotopic composition of nuclear or non-nuclear solid materials is performed in a variety
of fields for quality assurance in the production of nuclear fuels, nuclear safeguards, and non-proliferation
control, in material characterization, geology, and archeology. We have investigated the capability of ICPMS (inducted coupled plasma mass spectrometer) (Thermo Xseries 2) as a rapid analytical protocol for
uranium-isotope screening of nuclear solid samples. For this development we used a CRM (certificated
reference material) uranium oxide NBL-A129. Results for the isotopic (measured 235/238 ratio) display
no systematic bias. The precision and accuracy in combination there was no significantly different results
between the assays enables a rapid isotope screening of solid samples that is of particular interest to support
production of nuclear fuels and safeguard analysis.
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STUDY OF COMMERCIAL CHEMICAL ADDITIVES FOR CEMENTATION OF
RADIOACTIVE WASTE GENERATED IN PRESSURIZED WATER REACTOR
Vanessa Mota Vieira1, Clédola Cássia Oliveira de Tello1
Centro de Desenvolvimento da Tecnologia Nuclear (CDTN / CNEN), Contagem, Brazil, [email protected]
1
Cementation is a very useful process to solidify radioactive wastes. Depending on the waste it can be
necessary the use of chemical admixtures to improve the cementation process and its product. Admixtures
are materials, other than cement, aggregate and water, that are added either before or during the mixing to
alter some properties, such as workability, curing temperature range, and setting time. However there are
a large variety of these materials that are frequently changed or taken out of the market. In this changeable
scenario it is essential to know the commercially available materials and their characteristics. In this research
the effects of chemical admixtures in the solidification process has been studied. For the tests it was prepared
a solution simulating the evaporator concentrate waste, cemented by two different formulations, and three
chemical admixtures from two manufacturers. The tested admixtures were setting accelerators, setting
retarders and superplasticizers. The experiments were organized by a factorial planning 23 to quantify the
effects of formulations, of the admixtures, its quantity and manufacturer in properties of the paste and
products. The measured parameters were the density, the viscosity and the setting time of the paste, and the
product compressive strength. The parameter evaluated in this study was the compressive strength at 28
days of age, which is considered an essential security issues relating to the handling, transport and storage
of cemented waste product. The results showed that the addition of accelerators improved the compressive
strength of responses.
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Rapid determination of radiostrontium in groundwater using
automated radionuclide separation system
Hyuncheol Kim1, Kun Ho Chung1, Yoonhee Jung1-2, Geun-Sik Choi1, Mun Ja Kang1
Environmental Radioactivity Assessment Team, Korea Atomic Energy Research Institute, 2Korea University of Science and
Technology, Daejeon, South Corea, [email protected]
1
Radiostrontium is one of the main fission products, and can be released into the environment through nuclear
weapon testing, nuclear reprocessing facilities and nuclear accident and comes from authorized release
from nuclear power plant. Accurate determination of radiostrontium around above nuclear facilities is very
important in environmental risk assessment and therefore a large number of samples should be monitored
for radistrontium.
In Korea, the detection limit for Sr-90 in groundwater is required to 1 mBq L-1. Although a proportional
counter with very low background is employed, a large volume of groundwater (40 ~ 80 L) is needed to
satisfy the required detection limit. Because of lots of sample with large volume size, classical method such
as precipitation/nitric fuming acid for the analysis of radiostrontium is very tedious, time-consuming and
labor intensive work. Recently, combined procedure of cation resin / Sr resin has been attractive option for
the determination of radiostrontium in environmental sample like groundwater. A vacuum box is another
good option for reducing labor work, also, but it still needs manual operation and maintenance.
This study demonstrates the automated radionuclide concentrator which is named modular automated
radionuclide concentrator (MARC). It consists of four modules; valve module, control module, pumps module
and four columns module. It hanlds four samples at the same time. MARC was operated by our own control
software using LabView (National Instrument, USA). Cation resin was employed on MARC to concentrate
radiostrontium from groundwater. It was improved for large volume size sample from previously developed
automated system which is modular automated radionuclide separator (MARS)1. After the preconcentration
of radiostonrotum in the groundwater with MARC, it is purified with MARS using Sr-resin.
REFERENCE
1) Chung, K.H., S.D. Choi, G.S. Choi, and M.J. Kang, Appl Radiat Isotopes 81 (2013) 57-61.
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APPLICATION OF INSTRUMENTAL NEUTRON ACTIVATION ANALYSIS ON ICE
CORE SAMPLES
Giovanni Baccolo1-2-3, Massimiliano Clemenza3-4,
Maffezzoli3-4, Valter Maggi2, Ezio Previtali3-4
Barbara
Delmonte2,
Niccolò
University of Siena, 2Environmental Sciences Department, University of Milano-Bicocca, 3INFN section of Milano-Bicocca,
Physics Department, University of Milano-Bicocca, Milano, Italy, [email protected]
1
4
In the paleoclimate context the dust content in Antarctic ice is extremely important; physical and chemical
properties of the particles deposited in Antarctica are strictly related to different climatic parameters [1,2].
Measuring elemental and isotopical properties of the extremely reduced amount of dust found in ice cores is
still now a difficult challenge for the modern analytical techniques, like ICPMS and TIMS. This is particularly
true in relation to interglacial periods, when dust concentration reaches the lowest levels. Here we present a
new method based on instrumental neutron activation analysis (INAA) for the elemental characterization of
dust entrapped in ice cores. For the first time this nuclear-chemical technique is applied to Antarctic ice core
samples. In order to obtain the lowest detection limits and the entire analytical procedure was optimized,
paying great attention to reagents purity and to contamination sources during sample preparation. In order
to obtain high precision measurements INAA was coupled to a second technique, Coulter Counter, which
allows to measure the total particle content in a liquid [3]. Two samples from TALDICE ice core (Ross Sea/
Pacific Sector, Antarctica) were successfully analyzed and concentration of major and trace elements were
quantified in the same sample aliquots.
REFERENCES
[1] B. A. Maher, J. M. Prospero, D. Mackie, D. Gaiero, P. P. Hesse, Y. Balkansk, Earth Sci. Rev. 99 (2010) 61.
[2] F. Lambert, B. Delmonte, J. R. Petit, M. Bigler, P. R. Kaufmann, M. A. Hutterli, T. F. Stocker, U. Ruth, J. P. Steffensen, V.
Maggi, Nature 452(2008) 616
[3] U. Ruth, C. Barbante, M. Bigler, B. Delmonte, H. Fischer, P. Gabrielli, V. Gaspari, P. Kaufmann, F. Lambert, V. Maggi, F.
Marino, J. R. Petit, R. Udisti, D. Wagenbach, A. Wegner, E. W. Wolff, Environ. Sci. Technol. 42(2008) 5675
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
Ca2+, Mg2+, Ba2+ End 226Ra, in Scales Formed in Pipes from Industrial
Boilers
Claudia Miriam Braga Poggi1-2, Emerson Emiliano Gualberto de FARIAS1-2, Patrícia B. Silveira1,
Crescêncio Andrade Silva Filho1, Elvis Joacir de FRANÇA1, Maria Helena Paranhus Gazineu3,
Clovis A. Hazin1
Centro Regional de Ciências Nucleares do Nordeste/Universidade Federal de Pernambuco, 2Universidade Federal de Pernambuco,
Universidade Católica de Pernambuco, Recife, Brazil, [email protected]
1
3
In Brazil, the vast majority of industries use steam generated in boilers as the main source of energy. The water
employed in these processes is generally of subterranean origin, having high concentrations of calcium and
magnesium salts and traces of barium, which can co-precipitate with natural radioactive elements present
in the water, as is the case of 226Ra, radionuclide belonging to the uranium series. As no data were found in
the literature on the presence of natural radionuclides in scales from industrial boilers in general, this study
aimed to correlate the activity concentration of 226Ra with the concentration of calcium, magnesium, and
barium (belonging to the same chemical family), in samples of scale generated in industrial boilers in selected
municipalities in the State of Pernambuco. The activity concentration of 226Ra was determined by gamma
spectrometry. Calcium and magnesium, on the other hand, were determined by titration whereas barium was
determined by atomic absorption spectrometry. According to the results, no significant correlations were
observed between the pairs radio-calcium (r = 0.07) and radio-magnesium (r = 0.36), for a 95% confidence
level. However, there was a strong positive correlation between radium and barium, with an index r = 0.85.
The correlation between the concentration of barium and the 226Ra activity concentrations suggests that, due
to their chemical similarity, the water carries radio together with barium all the way from the origin up to
the scale.
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4th-INCC 2014 I 4th International Nuclear Chemistry Congress
DETERMINATION 238U AND 232Th IN MINERAL SANDS BY ALPHA SPECTROMETRY
Emerson Emiliano Gualberto De Farias1, Elvis Joacir De França1, Eliane Valentim Honorato1,
Clovis A. Hazin1
Centro Regional De Ciências Nucleares Do Nordeste - CRCN-NE/CNEN-PE, Recife, Brazil, [email protected]
1
In processing mineral sands for the extraction of kyanite, ilmenite, rutile and zircon, can have an increment
concentrations of uranium and thorium in end products. Thus, the present study aimed the techniques
of alpha spectrometry for the determination of 238U and 232Th in environmental samples, specifically in
mineral sands. The validation of the methodologies was carried out by using reference materials provided
by the International Atomic Energy Agency. For the determination of 238U and 232Th by alpha spectrometry,
samples were digested by alkaline fusion, spiked with 229Th and 232U tracers, purified by passing through
an ion exchange resin, electrodeposited on stainless steel disks and counted for 80,000 s. The results of the
analyses performed for mineral sands showed concentrations of uranium-238 ranging from 60 to 12,256
Bq.kg-1, with an average of 3,634 Bq.kg-1. The average activity concentration observed in samples of zircon
was 6,723 Bq.kg-1, while the average activity found for other mineral sands was of 545 Bq.kg-1, showing that
zircon sands deserve greater attention, from the standpoint of radiological protection, among the mineral
sands analyzed. Moreover, the determinations of thorium-232 showed activity concentrations ranging from
40 to 7,205 Bq.kg-1 with an average of 1,465 Bq.kg-1. Only two samples showed 232Th concentrations above
this value (both were of zircon sands), which reinforces the need for greater attention, from the point of view
of radiological protection, for samples of zircon.
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MOUNTING AND CALIBRATION OF A SCINTILLATION SYSTEM FOR
ENVIRONMENTAL RADON DETERMINATION
Emerson Emiliano Gualberto De Farias1, Elvis Joacir de França1, Clovis A. Hazin1
Centro Regional de Ciências Nucleares do Nordeste - CRCN-NE/CNEN-PE, Recife, Brazil, [email protected]
1
Radon is one of the most studied natural radionuclides due to its high relevance for radioprotection.
Moreover, radon can be used as a tracer for water deposits survey, for organic compounds leakage detection,
as well as an indicator of potential seismic events. Taking into account the needs of monitoring the radon
activity concentration in open and closed environments, active and portable detectors based on ionization
chamber and surface barrier sensors are available in the market. However, one of best systems for radon
detection is the solid scintillation detector. The present work aimed at the mouting and calibration of a radon
measurement system based on a scintillation detector of the Lucas Cell type. The apparatus consists of a
portable electronic system coupled to a photomultiplier tube, an external sampling pump and needle-type
valves connected to the scintillation cell. The detector was calibrated in a controlled environment, by means
of an in-house calibration chamber for radon detectors. The quality of the measurement procedure using this
detector was assessed in the same calibration chamber, with radon activity concentrations varying from 1
kBq.m-3 to 12 kBq.m-3. The obtained values were not statistically different at the 95% confidence level when
compared to the expected values determined with a reference detector.
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Radiation Chemistry
4th-INCC 2014 I 4th International Nuclear Chemistry Congress
A comparison of chemical dosimeters of reactor radiation for
the assessment of contributions of neutron and gamma radiation
to the total dose
Bohumil Bartoníček1, Jan Kučera2, Ingrid Pytelová1, Romana Svitáková3, Jiri
Horsky3, Martin Cabalka1
ÚJV Řež, a. s. 2Nuclear Physics Institute ASCR, 3Institute of macromolecular Chemistry ASCR, Czech Republic,
[email protected]
1
Knowledge of the total dose of reactor radiation, i.e., the mixed gamma and neutron radiation, is needed
for many applications of experimental nuclear reactors. Apart from experimentally demanding calorimetric
measurement of the radiation dose rate, chemical dosimeters are frequently used for this purpose. L-αalanine is an amino acid widely used for electron and gamma-ray dosimetric purposes. The alanine
dosimetric technique is based on the quantitative evaluation of stable free radicals in irradiated crystalline
α-alanine by ESR spectroscopy, also referred to as electron paramagnetic resonance (EPR) spectroscopy.
In our recent work [1] we decomposed the total absorbed dose in alanine into contributions of gammarays and neutrons of several energy groups. The latter task was accomplished by calculation using neutron
kerma factors for alanine for various neutron energies. We also presented a novel method of using alanine
for the assessment of a thermal neutron fluence rate based on measurement of the 14C radioactivity produced
by the reaction 14N(n,p)14C with thermal neutrons on nitrogen present in alanine (molecular formula
C3H7NO2). The 14C activity was measured by liquid scintillation counting (LSC). In this work we compare
performance of alanine with other chemical dosimeters, namely an aqueous solution of oxalic acid (OxA)
and perfluoro(methylcyclohexane) – PFMCH. The best agreement of the dose rates was obtained between
values measured with alanine, which is considered as a “gold standard” among chemical dosimeters, and
PFMCH. The advantage of OxA, the response of which is based on a decrease of OxA concentration due
to interaction of radiolysis products of water, is that no radioactive isotopes are formed upon irradiation
with neutrons or gamma-rays in a reactor. On the other hand, however, due to a dependence of the OxA
response upon the linear energy transfer (LET) of neutrons and gamma rays, a disagreement has been found
with the responses of alanine and PFMCH. Thus, use of alanine for determination of the total dose rate
of reactor radiation, and its possible decomposition into contributions of gamma-rays and neutrons using
kerma factors, can be recommended, namely due to the experimental simplicity of this method.
References
1. B. Bartoníček, J. Kučera, I. Světlík et al.: Extended use of alanine irradiated in experimental reactor for combined gammaand neutron-dose assessment by ESR spectroscopy and thermal neutron fluence assessment by measurement of 14C by LSC.
Appl. Radiat. Isotopes (2014) http://dx.doi.org/10.1016/j.apradiso.2014.02.002.
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EFFECTS OF IONIZING RADIATION ON THE PHYSICOCHEMICAL PROPERTIES
OF RED WINE CABERNET SAUVIGNON
Fellipe Souza da Silva1, Anderson R. L. SANTOS1, Octavio MACEDO1, Walsan W. PEREIRA1
Instituto de Radioproteção e Dosimetria IRD/CNEN, Rio de Janeiro, Brazil, [email protected]
1
Oenology has as its main purpose the continuous improvement of wine quality without jeopardizing its
proprieties, and the intent is to make these improvements using innovative new technologies. The red wine
Cabernet Sauvignon was selected for analysis in this study for having one of the highest consumption
rates in Brazil. In addition, the variable phenolic composition of this wine allowed us to ascertain changes
in flavor quality. The objective of the present work is to assess the effect of ionizing radiation on the
physicochemical properties of Cabernet Sauvignon that may lead to changes in wine quality, aging process
and other related characteristics. The analyzed data included alcoholic and total dry extract contents, density
and spectrophotometric measurements of absorbance at wavelengths of 420, 520 and 620 nm.
The samples used for this process were irradiated using an Argonaut reactor powered at 340 Watts and with a
thermal neutron fluence of 109 n/cm2.s. For the irradiation experiments, the samples were put into the reactor
chamber until the reactor reached criticality and for an additional 30 minutes while receiving radiation.
The irradiated samples were analyzed spectrophotometrically for changes in absorbance values as compared
to control samples. Increased absorbance values at 420 nm indicate an increase in tannin composition of the
wine and therefore a higher level of oxidation. Intriguingly, a rise in absorbance was also observed at 520
nm for the same test samples; which is inconsistent with published data on irradiated cachaça that showed
that anthocyanin levels dropped at 520 nm after irradiation.
Classical analytical tests of irradiated wines set as: density, alcoholic and ash contents were found to be
reduced by irradiation as compared to control.
In summary, the results indicated that the irradiation dose used in the study did not considerably affect the
analyzed wines. Future studies should evaluating dosing effects of irradiation on improving the quality of
the Cabernet Sauvignon.
REFERENCES
1)E. M. Yoshimura. “Física das Radiações: Interação da Radiação com a Matéria” Revista Brasileira de Física Médica. 2009;
3(1):57-67.
2)H. Johnson; “The Story of Wine.” Londres: Mitchell-Beazley, 1989. 480 p.
3)J. A. Pires; M. Scanholato. “Envelhecimento de Vinho Tinto por Irradiação Gama (Co60).” 2011. 87 p. Trabalho de
Conclusão de Curso (Tecnólogo em Biocombustíveis). Faculdade de Tecnologia de Piracicaba “Paula Souza”- Piracicaba,
2011.
4)M. A. Amerine; E. B. Roessler. “Wines – their sensory evaluation.” New York: W.H. Freeman, 1983. 432p.
5)T. Hashizume; E. Aquarone; U. A. Lima.; W. Borzani. “Alimentos e Bebidas Produzidas por Fermentação”; São Paulo:
Edgard Blücher, 1983. 5 v.
6)T. Hashizume et al. “Produção de etanol. In: Tecnologia do vinho. Biotecnologia Industrial: Biotecnologia na produção de
alimentos.” vol 4. São Paulo: Blucher, 2001.
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Ra, 228Ra AND 40K IN SCALES FROM BOILERS OF INDUSTRIAL INSTALLATIONS
226
Claudia Miriam Braga Poggi1-2, Emerson Emiliano Gualberto de Farias1-2, Patrícia B. Silveira1,
Crescêncio Andrade Silva Filho1, Elvis Joacir de França1, Maria Helena Paranhus Gazineu3,
Clovis A. Hazin1
1
Centro Regional de Ciências Nucleares do Nordeste, 2Universidade Federal de Pernambuco, 3Universidade Católica de
Pernambuco, Recife, Brazil, [email protected]
Many industrial processes involve the production of steam in boilers, which is sent through pipes to machines
and other equipment used in different sectors of the installations. The water commonly used in these
processes is groundwater, which generally has high concentrations of calcium and magnesium salts, that
can co-precipitate with naturally occurring radioactive elements such as 226Ra and 228Ra creating radioactive
scales, which are deposited in pipes, thus decreasing the efficiency of steam production. In addition, 40K
that is present in all soils and rocks with a concentration of about 0.012% of natural potassium can also be
concentrated in these scales. No data was found in literature relating to radionuclides present in the scales
formed on boilers in general. In this context, the purpose of this work was to determine concentrations of
226
Ra, 228Ra and 40K, in scales generated inside boilers from different industries in the cities of Caruaru,
Paulista and Goiana, Pernambuco. Determination of the radionuclides concentration was performed by
gamma spectrometry with an HPGe detector, calculating their specific activities. Activity concentrations of
226
Ra were in the range of < 1.4 (Detection Limit) to 1,328.0 ± 23.0 Bq.kg-1 and 228Ra activity concentrations
varied from < 1.8 (Detection Limit) to 265.5 ± 8.0 Bq.kg1. Activity concentrations of 40K were in the range
of < 14.6 (Detection Limit) to 288.1 ± 11.5 Bq.kg-1. All these activity concentrations were lower than the
limits established by the Brazilian Commission of Nuclear Energy for this type of matrix.
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IRRADIATION PROCESS APPLIED IN FISH SCALES: AN IMPROVEMENT OF ITS
CAPACITY FOR METALLIC SORPTION?
Renata Bazante-Yamaguishi1, Áurea Beatriz Cerqueira Geraldo1, Eduardo Moura1
Nuclear and Energy Research Institute (Instituto de Pesquisas Energéticas e Nucleares) - IPEN-CNEN-SP, São Paulo, Brazil,
[email protected]
1
Metal removal of environmental samples is an important study subject since this contamination category
may affect human health direct or indirectly. There are many known methods to proceed to the metal
removal1; each one has advantages and drawbacks. Metal precipitation is a simple and an efficient process
but it must be performed when high concentration of metal ions are present; ion exchange methods are fast
and the removal occurs efficiently even under very low concentration of metal ions (removal of ppb levels)
but can be an onerous method if great volumes must be treated; membrane methods are still very expensive
to be applied in water treatment due high costs of dialysis material and maintenance of dialysis system – so,
to be applied in effluents cleaning, the values are prohibitive.
Then, a good material to be applied in metal removal process must be low cost, easy to acquire and efficient
in its purpose. Generally, fibrous materials are selected for this finality because of their great surface area
that is a physical condition to perform the metal sorption. In this sense, cellulose fibrous biomaterials (like
sugarcane pulp and rice peel) and porous materials (like charcoal) are employed in this use.
Fish scales are a disposable byproduct of fisheries that have high potential to be used as ion metals sorption
material due to the fact that they have two regions with distinct properties: one external constituted by a
thin layer of low crystalline hydroxiapatite – this layer has high surface area and many studies indicate that
this region has an efficient metal removal characteristic and one internal thicker layer with fibrous nature
done by the collagen fibers2,3. Fish scales as a raw material acts efficiently in metal removal mainly at high
concentrated solutions; there is a work that indicates an enhancement of sorption effect when fish scales are
treated with gluteraldehyde4.
In this work, fish scales were submitted to ionizing radiation process. Our group investigated the effect of
dose rate and absorption dose related to its ion metal sorption capability analyzing physical and chemical
parameters of fish scales before and after irradiation process.
REFERENCES
1) R. Bazante-Yamaguishi, E. Moura, J.E. Manzoli, A.B.C. Geraldo, J. Radiation Phys. and Chem. 94 (2014) 133-136.
2) G.E. Coote, R.W. Gauldie, I.F. West, Nuclear Instruments and Methods in Physics Res. 54 (1991) 144-150.
3) J. F. Villanueva-Espinosa, M. Hernández-Esparza, F. A. Ruiz-Trevin, Ind. Eng. Chem. Res. 40 (2001) 3563-3569.
4) K. O. Moura, E.F.S. Vieira, A.R. Cestari, J. Appl. Polym. Sci., 124 (2012) 3208-3221.
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STUDY OF HYDROPHILIC MATERIALS AS TISSUE EQUIVALENT PHANTOMS FOR
POSITRON EMISSION TOMOGRAPHY
M. Alkhorayef1
Department of Radiological Sciences, College of Applied Medical Sciences, King Saud University, Riyadh, Saudi Arabia,
[email protected]
1
Positron emission tomography (PET) is a nuclear medicine procedure allowing biochemical processes to be
investigated by in-vivo imaging. Tissue equivalent materials have generated great interest in the diagnosis
and treatment of cancer. By controlling the hydration level and oxygen concentration, it may be possible
to imitate various types and different disease stages of tissues, as well as the extent of tissue hypoxia. This
study describes the preparation and methods employed to determine oxygen levels in different types of
cross-linked hydrophilic co-polymers with a view to extend this further in samples with low concentrations
of ‘hypoxia’ and at normal levels of oxygen ‘normoxia’ based on in-vitro measurements. The physical
characteristic of hydroxyethyl methacrylate (HEMA) and methyl methacrylate/Vinyl pyrrolidone (MMAVP) were studied by measuring the hydration rate in biological fluids. The relative yield of 3-to-2 photon
annihilation was determined using the positron emitter, Na-22 with lanthanum bromide (LaBr3:Ce(5%))
scintillation detector. The Na-22 source used has a positron yield of 90.4% and a gamma-ray energy at
1274keV of relative intensity 99.9%, emitted almost simultaneously. The energy resolution and the intrinsic
photopeak efficiency figures for LaBr3:Ce were (3.37±0.08)% and (29.1±0.8)%, respectively for the 511keV
annihilation energy. From the gamma ray spectra recorded the mass attenuation coefficient and the relative
yield of 3-to-2 photon annihilation were calculated and discussed.
Key word; hydrophilic materials, 3-to-2 photon annihilation, positron emission tomography
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EPR Investigation of Butylated Hydroxytoluene and Estimated
Uncertainty Associated with Different Measurements
M Alkhorayef1-2, A. Mansour3-4
Department of Radiological Sciences, College of Applied Medical Sciences, King Saud University, 2Centre for Nuclear and
Radiation Physics, Department of Physics, University of Surrey, 3National Center for Radiation Research and Technology, Atomic
Energy Authority, 4INAYA Medical Collage Riyadh, Saudi Arabia, [email protected]
1
EPR dosimetry is characterized by its non-distractive read-out and the possibility the dose archival. Butylated
Hydroxytoluene (BHT) has specified EPR signal developed under gamma irradiation in the dose range 0.1100 kGy. The EPR spectrum of BHT was studied and assigned, and change in the BHT EPR spectrum as
a result of the change in EPR measurements were quantified. An EPR investigation of radiation induced
radicals in BHT samples revealed that there are two types of radicals produced after exposure to gamma
radiation (Co-60). Uncertainties associated with different managements (stability of EPR spectrometer,
reproducibility, orientation effect, vertical positioning and uniformity of dosimeters) using BHT samples
were discussed and tabulated. It was found that BHT possesses good dosimetric properties using EPR
spectroscopy in low and high doses in addition to its characterized by low uncertainty (2.86 %).
Key word; BHT - Gamma rays – EPR – Uncertainty
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IONIZING RADIATION INFLUENCE IN LOW DENSITY POLYETHYLENE WITH
CHARCOAL BLACK PIGMENT
Leonardo Gondim de Andrade E Silva1, Maurício César Ferreira Santos2
Instituto de Pesquisas Energéticas E Nucleares, Ipen-Cnen/Sp, São Paulo, Brazil, [email protected]
1
In this work we have studied the development of a charcoal black pigment which has characteristics similar
to those already used in the market of thermoplastic processing. Nowadays the most widely used black
pigment in thermoplastic processing industries is carbon black, that such obtaining process, generates much
toxic waste and when released into the atmosphere, it increases air pollution. The aim of this study was
to obtain a charcoal black pigment, studying the incorporation of this pigment obtained in low density
polyethylene, ( LDPE ) and also study the influence of ionizing radiation in LDPE with black pigment.
Thus, charcoal and LDPE were used as raw-material. Subsequently, the black pigment was incorporated into
LDPE obtained by the injection process. The samples were irradiated by electron beam at doses of 100, 200,
300 and 400kGy. Then the non irradiated and irradiated samples were characterized by mechanical analysis.
The black pigment was easily obtained from a renewable source, with low cost and presented compatible
colorimetric properties and approached to carbon black. The incorporation of the pigment into the polymer
matrix during the injection process was easy, distributing it evenly. Regarding the irradiated samples it can
be said that there was an increasing in the majority of the properties, previously studied. Depending on
the type of piece to be manufactured and which properties are more important, it can be said that one can
irradiate the black pigment in LDPE with more suitable doses.
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Radioecological and Geochemistry
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SEDIMENTS FROM THE NORTH COAST OF THE GULF OF MEXICO:
GEOCHEMICAL CHARACTERIZATION AND FRACTIONING
Brenda Beatriz Estañol Díaz1, Trinidad Martínez Castillo1, Miguel Ángel Zúñiga Pérez1,
Samuel Tejeda Vega2, Graciela Zarazúa Ortega2, Juan Manuel Navarrete Tejero1
Departamento de Química Inorgánica y Nuclear, Facultad de Química, Universidad Nacional Autónoma de México, 2National
Institute of Nuclear Research, México, Mexico, [email protected]
1
Seven marine sediment samples from the North Coast of the Gulf of Mexico were collected in October 2012
at water depths between 50 m and 2500 m. Physical and chemical properties were determined in laboratory
by standard methods, including organic carbon, carbonates, total carbon, pH and conductivity. Granulometric
analysis show that 90% to 97% of particles are lesser than 74 µm (silts and clays). Concentrations of K, Ca, Ti,
Mn, Fe, Cu, Ni, Cu, Zn, Ga, and Pb in bulk samples were analyzed by energy-dispersive X-ray fluorescence
technique (EDXRF). Certified Reference Material was processed and analyzed at even conditions as qualitycontrol method1. The selective leaching technique proposed by Tessier2 was used to extract metals into
five operationally-defined fractions: F1, exchangeable fraction; F2, carbonate fraction; F3, Fe-Mn oxides
fraction; F4, organic matter fraction and F5, residual or lithogenic fraction. Metals associated to each fraction
were measured by ICP-OES. Differences in average concentrations were evaluated by means of one-way
analysis of variance and Kruskal–Wallis test, by using the Statgraphic Centurion (version XV) software.
Enrichment Factor (EF) and Geoaccumulation Index (IGeo) were calculated, concentration values for almost
all of the analyzed elements, are similar to those of Earth’s crust3, so giving a baseline data for the sampling
zone. Only a few elements count for the exception and they are discussed too. All of them show lesser values
than those reported for the most contaminated zones in the South Coast of the Gulf of Mexico4,5.
REFERENCES
1) B. Estañol, Tesis de Licenciatura. Facultad de Química. UNAM (2014)
2) A. Tessier, P.G.C. Campbell, M. Bisson, Anal. Chem 51, 7 (1979) 844.
3) J.M. Martin, M. Meybeck, Mar. Chem. 7 (1979) 173.
4) F.G. Vázquez, V.K. Sharma, Marine Pollution Bull. 48 (2004) 87.
5) J.H. Trefy, B.J. Presley, Environ. Geol. 1 (1976) 283.
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Estimation of 220Rn efective dose in México
Trinidad Martínez Castillo1, Pedro GONZALEZ2, Alejandro Ramírez Chávez1, Omar Yahir
MORALES1, Juan Manuel Navarrete Tejero1
Facultad de Química, Departamento de Química Inorgánica y Nuclear, Universidad Nacional Autónoma de México, 2National
Institute of Nuclear Research, Ciudad de México, Mexico, [email protected]
1
Since 1992 the Chemistry Faculty of the National University of Mexico has been performing studies about
environmental natural radioactivity1,2, gamma, radon and thoron levels in the Metropolitan Zone of Mexico
Valley (MZMV) and other zones like the Metropolitan Zone of Guadalajara (MZG). This work reports
220
Rn (thoron) effective dose assessed based in the formula given by the National Scientific Committee
(UNSCEAR)3 taking into account the dose conversion factor of 40 nSv (per Bqm-3 h-1) for thoron equilibriumequivalent concentration (EEC). Thoron and Radon concentration was measured previously4 using “S”
chambers loaded with blue short term electrets (E-PERM, “SSTB” configuration). A Quality assurance
Program was installed. Results for the Effective dose from thoron were 0.459 mSv y-1 and 0.683 mSv y-1,
in the MZMV and the MZG respectively. A comparison with the world average reported by UNSCEAR is
discussed.
REFERENCES
1) T. Martinez, L. Cabrera, M. Navarrete, J.J. García Reséndiz, P- Gonzalez, A. Ramirez, U. Martinez. J. Radioanal. Nucl.
Chem, 193, 2 (1995) 259.
2) O.Y. Morales, T. Martinez, P. Gonzalez, M. Navarrete, L. Cabrera, A. Ramirez, . J. Radioanal. Nucl. Chem, 280 No. 2 (2009)
431.
3) United Nations Scientific Committee on the Effects of Atomic Radiation. UNSCEAR 2006. Annexe E, sources-effects
assessment for radon in homes and workplaces. United Nations (2009)
4) T. Martínez, M. Navarrete, P. González, A. Ramírez, Radiat. Protect. Dosim. 111, 1 (2004) 111
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SEQUENTIAL EXTRACTION APPLIED TO PERUIBE BLACK MUD
Jefferson Koyaishi Torrecilha1, Marycel Elena Barboza Cotrim1, Paulo S. Cardoso da SILVA1
Instituto de Pesquisas Energéticas e Nucleares IPEN - CNEN/SP, São Paulo, Brazil, [email protected]
1
The Peruíbe Black Mud is used in therapy such as psoriasis, dermatitis periphereal, acne, seborrhea, myalgia,
arthiritis and rheumatic non-articular processes. This material is characterized by its fine particles organic
matter, sulphate reducing bacteria content and high reduction potential. Although being considered natural,
muds may not be free of possible adverse health effects when used for therapeutic purposes, such as toxic
chemicals elements. In therapeutic treatments involving clays, they are used in mud form called peloid,
obtained after maturation process. The sequential extraction is well known useful tool to evaluate the
behavior of trace elements in different matrices. So, a sequential extraction to fractionate the Peruíbe Black
mud in geochemical specific fractions were used to check which elements and how much of them are present
in each soluble, organic matter, iron oxi-hydroxide and residual fraction. To soluble, organic matter and iron
oxi-hidroxide fractions obtainment acetic acid, hydroxylamine hydrochloride and ammonium acetate were
used, respectively. Considering the various sequential extraction methods the BCR-701 (Community Bureau
of References) were chosen because it is considered the most reproducible between them. The determination
of the major and trace elements concentration in the in natura and maturated clays that constitute the Peruíbe
Black Mud ICP-EOS were applied to each fraction obtained in the sequential extraction.
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SOIL CONTAMINATION OF PROCESS LIQUID FROM THE INDUSTRIAL
PRODUCTION OF AMMONIUM DIURANATE
Hector Hugo Silva Medrado1, Nichele Cristina de Freitas Juchneski1, Ricardo A. QUEIROZ1,
Tatiane P. AMORIM1, Wanderson S. ARAÚJO1, Renata R. CARVALHO1, Pedro L. S. DIAS1
Indústrias Nucleares do Brasil, Caetité, Brazil, [email protected]
1
Accumulation and transport of radionuclides through the soil from accidental spills depends on the
characteristics of the contaminant and the soil. Through the characterization of a simulated spill, it is possible
to visualize the interaction of the soil with a contaminant and thus promote the appropriate preventive and
corrective actions. The process of beneficiation of uranium occurs through several stages, which generate
liquid containing concentrations of radionuclides and stable chemical species, potential soil contaminants
in cases of accidental spills. The aim of this study was to evaluate and predict the behavior of a liquid, as
described above, in contact with the first layer of soil (sandy clay).
Assays were conducted by passing a contaminant aqueous through layers of soil (clay) of 5, 10 and 15
cm Measurements of pH1,2, chloride3,4, nitrate3,4, sulfate3,4, and natural uranium were carried out in the inlet
liquid, collected liquid, in the clay and pre and post contact with the initial solution. From the results, it
was possible to determine the changes in the soil caused by the net input, the chemical characteristics of
the liquid collected after contact with the clay and migration rates of chemical species analyzed. In order to
check the possible influence on the migration of uranium due to the presence of chloride, nitrate and sulfate,
the percolation of a solution of uranium standard though a 5-cm-layer of clay took place.
The results show that the percolation time is inversely proportional to the mass and height of the clay layer.
The ratio of 60 mL of liquid per 5 cm layer of clay was used. After complete percolation, it was found that
the volume of collected fluid is linearly proportional to the added volume of the column clay. Chemical
analysis indicated that the liquid inlet with high concentrations of chloride (49,877.0 mg/L), nitrate (1,928.8
mg/L), sulfate (131,794.7 mg/L) , uranium (801.7 Bq/L) is released with an exponential decrease in all
parameters with the increase of the height and mass of the clay layer. When the highest layer of clay (15 cm)
was tested, all parameters reach less than 1 % of its input value. The relative rates of migration show that
nitrate anion diffuses faster in the soil, followed by the chloride and sulfate. It was also found that the OHions move very slightly in the direction of flow of percolating liquid, once the liquid inlet has a pH of about
8 and all output fluids are around pH 5. Finally, it was found that there is an increase in the rate of migration
of uranium when it is dissolved in aqueous solution with stable species (Cl-, NO3- and SO42-). It is believed
that these species favor the migration of natural uranium due to complexation reactions3 and decompression
of the clay.
This assay can be used in the evaluation of potential spills of aqueous solutions containing uranium and
stable species in order to subsidize remedial actions in order to minimize environmental risks.
REFERENCES
1) APHA, Standard Methods for the examination of water and wastewater (1998)
2) USEPA 9045D - Solid and Waste pH, R4 (2004)
3) USEPA 9056A - Determination of Inorganic Anions by Ion Chromatography, R1 (2007)
4) Tex 620J - Determining Chloride and Sulfate Contents in Soil (2005)
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ACTIVATION ANALYSIS IN GEOCHEMICAL CHARACTERIZATION OF
SEDIMENTS RELATED TO THE RIES IMPACT CRATER
Zdeněk Řanda1, Jiří Mizera1, Karel ŽÁK2, Roman Skála2, Jan Kameník1
Nuclear Physics Institute, Academy of Sciences of the Czech Republic, 2Institute of Geology, Academy of Sciences of the Czech
Republic, Řez, Czech Republic, [email protected]
1
The Ries impact crater (Nördlingen, Germany) has unequivocally been accepted as the parent impact
structure to the Central European tektites – moldavites, based on correspondence of their age (~14.5 Ma)
and similarity of chemical composition of moldavites with their supposed source materials in the target
area. The pre-impact unconsolidated surface sediments in the Ries area dated to the Middle Miocene, the
so-called Obere Süßwassermolasse (OSM), have been suggested as the major source material.
Within the frame of a research project aimed at clarifying the issue of unambiguous assigning source materials
of moldavites and processes of their chemical differentiation, 34 samples of unconsolidated sediments of
Miocene age and bedrock samples of Mesozoic age were collected in the Ries area. Most attention was
paid to various types of the OSM sediments. Marginally also Miocene karst residues and Triassic and
Jurassic sedimentary rocks were sampled to obtain a data set for all principal unconsolidated sediments and
selected rock types, present in the target area at the time of the impact. Such a complete data set of potential
components will allow modeling of moldavite chemical composition as a mixture of these components.
In the dried and homogenized samples, total and carbonate carbon contents and the loss on ignition were
determined. Their detailed geochemical characterization was based on determination of about fifty major
and trace elements, using various modes of instrumental neutron and photon activation analyses (INAA and
IPAA, respectively).
The geochemical data were compared in terms of major elements (Si, Al, K, Na, Fe, Mg, Ca) with the
data obtained previously by INAA and IPAA for a large representative collection of moldavites. Despite
similarity in the chemical composition of some OSM samples with moldavites, there are some significant
differences in the major element contents, namely significantly higher contents of Al, Na and Fe, and lower
contents of K, Ca and Mg in the sediments than in moldavites. These differences can be partly solved by
recalculation of the composition of the sediments to their volatile-free bases, since the moldavites contain
extremely low contents of water and carbon, which escaped during the impact process and moldavite
formation. Nevertheless, another component rich in K, Ca and Mg is highly probable. Recently, we presented
a hypothesis of contribution to the moldavite source materials of an unoxidable residue formed by pyrolysis
and oxidation of biomass from the Earth’s surface during the meteorite impact, which would contribute to
high K, Ca and Mg levels in moldavites. Currently performed mixing calculations, which assume common
clay minerals, carbonates, silica and ash from biomass as the end members of the mixture, show that an
average moldavite composition can successfully be modeled if the mineral compositions are recalculated
to their volatile-free bases. The “biogenic” component may represent only a minor fraction in majority of
moldavites, but may become more important in modeling composition of moldavites with extremely high
K/Na ratios.
The study was supported by the projects 13-22351S and 205⁄09⁄0991 of the Czech Science Foundation.
Authors thank Prof. Dr. Kurt Heißig from the Ludwig-Maximilians-Universität, München, for his assistance
during sampling in the Ries area.
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Geographical discrimination of Brazilian stingless bees by
instrumental neutron activation analysis
André Luis Lima de Araújo1, Elisabete A. De Nadai Fernandes1, Márcio Arruda Bacchi1,
Gabriel Ádrian Sarriés1, Andrés Enrique Lai Reyes1
Nuclear Energy Center for Agriculture, University of São Paulo, Sorocaba, Brazil, [email protected]
1
The decimation of bee populations around the world, known as the colony collapse disorder (CCD), has
brought serious ecological and agro-economic impacts, since several species of plants depend on bees for
pollination. Scientists have speculated about the possible causes of the colony collapse, without a definitive
answer. One widely accepted hypothesis is the contamination of the environment with toxic substances.
The habits of foraging large areas and storing food would extend the contact of social bees with pollutants
and prolong the harmful effects. In fact, considering the high metabolic activity, bees can concentrate
pollutants in their tissues, which make them suitable as biomonitors of environmental quality. In Brazil,
there are about 300 species of social stingless bees producing honey (tribe Meliponini), most presenting
endemic distribution due to the intrinsic relationships developed with certain botanical groups. For such
endemic species, deforestation and destruction of habitat have aggravated the occurrence of CCD. This
study investigated the bioaccumulation of chemical elements in stingless bees sampled in five Brazilian
states, i.e. Bahia, Minas Gerais, Rio Grande do Norte, Santa Catarina and São Paulo, comprising 70 hives
of the species Melipona quadrifasciata, Melipona scutelaris, Melipona mandacaia, Melipona capixaba,
Melipona rufiventris, Melipona compressipes, Melipona bicolor, Nannotrigona testaceicornis, Tetragona
clavipes and Scaptotrigona sp.. Metabolized pollen, the main source of chemical elements for bees, and
honey were also collected from each hive to assess bioaccumulation factors. Instrumental neutron activation
analysis allowed the determination of Br, Ca, Co, Cs, Fe, La, Na, Rb, Sc and Zn in honey samples, Br, Ca,
Co, Cs, Fe, K, La, Na, Rb, Sc, Se and Zn in pollen samples, and As, Br, Co, Cr, Cs, Fe, K, La, Na, Rb,
Sb, Sc, Se and Zn in bees samples. Ash, conductivity, moisture and pH were also determined in the honey
samples. Chemometric analysis indicates that the elemental composition of honey, pollen and stingless bees
themselves could discriminate their geographical origin. Arsenic appeared above detection limits only in
bees collected from areas of high human activity. The results have demonstrated the potential of stingless
bees as a tool for assessment of environmental quality.
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Study of 222Rn, 226Ra and 238U concentration in samples from
groundwater aquifer belonging to the Osamu Utsumi mine, UTM /
Caldas-MG
Heber Luiz Caponi Alberti1, Nivaldo Carlos da Silva1, Peter Marshal Fleming2, Sueli Yoshinaga
Pereira3, Flavio Henrique de Souza Moreira4
Comissão Nacional de Energia Nuclear (LAPOC / CNEN), 2Comissão Nacional de Energia Nuclear (CDTN/ CNEN),
Universidade Estadual de Campinas , 4Universidade Federal de Alfenas, Guaxupe, Brazil, [email protected]
1
3
The present study focuses the quantification of the concentration of radon in groundwater aquifer around first
uranium mine of Brazil located in Plateau Pocos de Caldas. This mine is in the process of decommissioning.
The 222Rn, 226Ra and 238U are present in any rock formation in the soil and in groundwater. The 222Rn
originates from 226 Ra and decays by alpha radiation to 218 Po, that continues following the cycle of
decay emitting alpha and beta particles until stabilization in 210Pb. In this study was collect 15 samples
of groundwater between the months of May and June 2013. Theses sampling was collect in monitoring
wells located in waste rock 4, pit mine and around these impacted sites. In all samples was determined the
concentration of 222Rn, 226Ra and 238U in Becquerel per liter. The sample of groundwater in monitoring
wells was performed follow the norms and standards of ABNT NBR 15847. The analyses of 238U and
236Ra concentrations in water were available in the Poços de Caldas Laboratory – LAPOC/CNEN. For
quantification of concentration 222Rn in water was used the monitor of radon AlphaGUARD that captures
and quantifies the alpha particles and the accessories Aquakit and AlphaPUMP. In addition to measuring
the concentration of 222Rn were measured main physico-chemical parameters of groundwater at each
monitoring well. 222Rn found values ranging from 199 to 1763.2 Bq / L. These results could use 222Rn as
a natural tracer.
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A comparative study using Alfa-Guard and liquid scintilation
counting to determine 222Rn in spring water in Poços de CaldasBrazil.
Flávio Henrique de Souza Moreira1-2, Heber Luiz Caponi Alberti2, Maria Helena Tirollo
Taddei2, Nivaldo C. Silva2, Peter Marshall Fleming3
Universidade Federal de Alfenas – Campus Poços de Caldas, 2Comissão Nacional de Energia Nuclear (LAPOC/CNEN),
Comissão Nacional de Energia Nuclear (CDTN/CNEN), Pocos de Caldas, Brazil, [email protected]
1
3
This study is a comparison of methodologies for determining the concentration of radon (222Rn), held in
natural water sources in the city of Poços de Caldas, Minas Gerais-Brazil. The city of Poços de Caldas
is located within an area affected by reactivation of volcanic processes occurring during the formation of
massive zone. This is the largest alkaline complex in Brazil, the great stratum-alkaline volcano of Poços de
Caldas is a volcanic caldera with about 30km in diameter consisting of plutonic igneous rocks, breccias and
mineral spills that have reached the surface. Sampling was carried out in natural water sources distributed
throughout the city, these determined the concentration of water present in 222Rn in Becquerel per liter,
according to the requirements and parameters of the ABNT NBR 15847. Radiation levels found in natural
sources were interpreted in accordance with the limits for total doses absorbed by an individual and the
standards for radiological protection of the National Nuclear Energy Commission, CNEN. The determination
of the concentration of 222Rn (the sixth son of the decay of 238U) present in water was possible through the
capture of alpha particles emitted by the decay of the element, we used the accessories for measuring radon
in water Aquakit AlphaPUMP and, in combination with monitor radon AlphaGUARD. Both samples to be
measured by liquid scintillation method were taken. At one point in the central region of the city values
reached 215.72 Bq/L measured in AlphaGUARD and 195.78 Bq/L method in liquid scintillation. The final
results of the study and also the complete methodology will be presented in this paper.
REFERENCES
1)Cipriani, Moacir. “Mitigação dos impactos sociais e ambientais decorrentes do fechamento definitivo de minas de urânio”,
Instituto de Geociências UNICAMP- Campinas, SP: [s.n.], 2002.
2)Queiroz, Ana Paula; “ABNT NBR 15847 - Amostragem de água subterrânea em poços de monitoramento - Métodos de
purga”, Comissão de Estudo Especial Temporária de Avaliação da Qualidade do Solo e da Água para Levantamento de
Passivo Ambiental e Avaliação de Risco à Saúde Humana, CEET- 00:001.68.
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Gamma-ray emitter radionuclides in soils from an institute of
technology campus in São Paulo city
Santiago Scarcelli Santos1, Marcelo Francis Máduar2, Pedro Miranda Junior1
Instituto Federal de Educação, Ciência e Tecnologia de São Paulo (IFSP), 2Instituto de Pesquisas Energéticas e Nucleares (IPENCNEN/SP), São Paulo, Brazil, [email protected]
1
Mankind is continuously submitted to the environmental radiation, from both artificial and natural
sources. Among the natural sources, an important contribution arises from the gamma radiation emitted
by radionuclides present in the soil, especially 40K and those from the 238U and 232Th series. In this work, a
radiological characterization of the soil from the São Paulo city campus of the Instituto Federal de Educação,
Ciência e Tecnologia de São Paulo (IFSP), a federal institute of technology, was performed. At the site, 30
superficial soil samples were collected and analyzed in order to determine their pH, according to procedures
adopted by EMBRAPA1. The sampling points were chosen to be uniformly distributed, in order to be
representative of different local characteristics, such as vegetation coverage and visual color and aspect of
the soil. The sampling site was mapped and georeferenced, excavation of perforations with 50 cm diameter
and 50 cm depth was done, and the samples were collected within a depth range of 25 – 50 cm. They were
sieved with a mesh aperture of 6 mm in order to remove impurities and dried in oven. After drying, the
samples were again sieved with mesh aperture 2.4 mm and the passing fraction was taken for analysis. In
order to determine the contents of natural gamma-ray emitters present in the soil of the studied site, the
samples were analyzed by using the technique of high-resolution gamma-ray spectrometry with highpurity
germanium detectors (HPGe). The pH of the samples varied in the range from 5.56 ± 0.06 to 7.26 ± 0.05.
Activity concentrations of 226Ra, 228Ra, 210Pb and 40K were found in the following ranges: for 226Ra, 39.4 ±
1.2 Bq.kg-1 to 47.9 ± 1.2 Bq.kg-1; for 228Ra, 84.3 ± 2.4 Bq.kg-1 to 127 ± 3 Bq.kg-1; for 210Pb, 47 ± 8 Bq.kg-1
to 61 ± 8 Bq.kg-1; for 40K, from below 40 Bq.kg-1 to 248 ± 15 Bq.kg-1. Considering the entire samples set,
very strong correlations of 228Ra and 40K activity concentrations with pH were found, negative for 228Ra (r =
-0.855) and positive for 40K (r = 0.845). For 228Ra concentration, a strong negative correlation (r = -0.614)
and for 210Pb, a moderate negative correlation (r = -0.345) with pH were found. The results are in agreement
with the order of magnitude of reported results from worldwide soils and could contribute as input data to
the information system on environmental radioactivity established in Brazil2.
REFERENCES
1) EMBRAPA. EMPRESA BRASILEIRA DE PESQUISA AGROPECUÁRIA. CentroNacional de Pesquisa de Solos. Manual
de métodos de análise de solo. 2. ed. Rio de Janeiro:Embrapa Solos, 1997.
2) Tadeu A. de A. Silva, Sérgio de A. Gonzalez, Rócio G. dos Reis, Luiza M. de H. eVasconcellos, Dejanira da C. Lauria.
GEORAD: Sistema de gestão de dados de radioatividadeno meio ambiente, IRPA 2013, Rio de Janeiro, RJ, Brazil, April 1519, 2013.
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RADIOLABELED THERMORESPONSIVE POLYMERS FOR LOCAL THERAPY
Veronika Felklová1, Martin Hrubý1, Jan Kučka1, Pavla Jendelová2, Pavla Poučková3
Institute of Macromolecular Chemistry, Czech Academy of Science, v.v.i., 2Institute of Experimental Medicine, Academy of
Science of the Czech republic, v.v.i, 3Institute of Biophysics and Informatics, First Faculty of Medicine, Charles University in
Prague. Prague, Czech Republic, [email protected]
1
Thermoresponsive polymers with lower critical solution temperature (LCST) are water-soluble at room
temperature and reversibly precipitate at higher temperature, e.g. at body temperature (37°C)1. This property
may be advantageous for drug and gene delivery, tissue engineering or local therapy. After injection of
such polymer solution these polymers create a depot at the site of application, which is caused by phase
separation at body temperature2. Local application of the thermoresensitive polymer with radionuclide may
be used for local radiotherapy – brachytherapy3. This treatment of solid tumor is gentle for whole body,
because high radiation doses are delivered to damaged tissue only.
Iodine-131-labeled thermoresponsive polymer [poly(N-isopropylacrylamide)] was used as injectable
brachytherapy in the experiment with murine xenograft model (PC3 human prostate adenocarcinoma). The
two radiation doses were used, 2 MBq/mouse and 25 MBq/mouse. The lower dose caused retardation of
tumor growth compared to untreated controls while the higher dose caused reduction of tumor volume.
In both cases there was no local inflammation. The differences between trated groups and controls were
statistically significant on level α = 0.05.
The results of the local radiotherapy were the basis for the enzyme delivery to neuronal damage treatment.
In these cases the thermoresponsive polymers were conjugated with superoxid dismutase and glutamate
oxidase. These enzymes are able to degrade superoxide and glutamate, respectively, which are the main
mediators of posttraumatic secondary damage of neural tissue.
The authors thank the Academy of Sciences of the Czech Republic, grant No. M200501201.
REFERENCES
1)M. Hrubý, J. Kučka, et al.; Journal of Controlled Release 119, (2007), 25.
2)M. Hrubý, J. Kučka, et al.; Journal of Applied Polymer Science 111, (2009), 2220.
3)M. Hrubý, P. Poučková, et al.; Europian Journal of Pharmaceutical Science 42, (2011), 484.
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STANDARDIZATION OF 153Sm BY COUNTING ANTICOINCIDENCE LIVE-TIMED
AND EXTENDIBLE DEAD-TIME
Adilson da Silva Laranjeira1, Carlos José da Silva1, José Ubiratan Delgado1, Paulo Alberto
Lima da CRUZ1, Roberto POLEDNA1, Ronaldo L. da Silva1, Antônio Eduardo de Oliveira1
Instituto de Radioproteção e Dosimetria/Comissão Nacional de Energia Nuclear (IRD/CNEN), Rio de Janeiro, Brazil,
[email protected]
1
Brazil has been using the 153Sm (EDTMP) since 1995 to control bone-pain, due breast and prostate
cancer metastasis but without a radioactivity absolute standard to ensure a reliable dose administered to
patients. The goal this study was to produce activity national standard of 153Sm, to integrate LNMRI-IRD
comparison program with nuclear medicine services and radiopharmaceutical producers in Brazil, to ensure
the traceability measurements. 153Sm decays by β- towards 153Eu, with 3 main branches and at least 15
other branches very weak, and has a half-life of 1.92855 (5) (d). Higher-intensity γ emissions are 69.7 keV
(4.69%) and 103.18 keV (29.19%). The activity per unit mass was standardized by anticoincidence absolute
standardization system and compared with results obtained by CIEMAT/NIST method. Both methods use
liquid scintillation to detect beta particles. The results obtained for two standardization held agreed to 0.13%
and 0.15%. The uncertainties obtained by anticoincidence system and CIEMAT/NIST methods are 0.42%
and 0.29%, 0.38% and 0.46%, respectively, for k = 1. To retain absolute standardization data, a calibration
factor was determined by secondary standardization system with ionization chamber 4πγ, with uncertainty
of 0.45%, k = 1. The half-life of 153Sm was also determined with 4πγ ionization chamber and value obtained
was 1.9291 (11) d, and -0.03% difference relative to reference value 1.92855 (5) (d). Radionuclide impurities
were not found in 153Sm solutions. 153Sm standardization will provide to nuclear medicine services and
producers of radiopharmaceuticals in Brazil as a reference standard of radioactivity to ensure the traceability
measurements.
REFERENCES
1) C. J. da Silva et al., Applied Radiation and Isotopes. 70 (2012) 1924.
2) J. Bryant, Applied Radiation and Isotopes. 13 (1962) 273.
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Hf as a competitor in the synthesis of 177Lu-DOTATATE
José de Souza Caldeira Filho1
Centro de Tecnologia das Radiações. Instituto de Pesquisas Energéticas e Nucleares - IPEN/CNEN/SP , São Paulo, Brazil,
[email protected]
1
Objective: This study was performed to show the interference of Hf, decay product of 177Lu, in the synthesis
of 177Lu-DOTATATE.
Methods: The experiments were performed following the decay of 177Lu: 1.64 T1/2, 2.68 T1/2 and 4.03 T1/2.
The molar ratio Lu:DOTATATE used in the synthesis of the radiopharmaceutical 177Lu-DOTATATE was
calculated for each decay, in two situations: 1) not considering the influence of Hf as a competitor.; 2)
considering the influence of Hf as a competitor. Considering these two situations, the synthesis of 177LuDOTATATE (n=3) was carried out in ammonium acetate buffer 0.5 M, pH 7.0, temperature 95oC, 350 rpm
for 30 minutes. The radiochemical purity (%) of the radiopharmaceutical was measured by chromatography
technique, was used ITLC-SG in sodium citrate buffer 0.1M, pH 5.0.
Results :
Table 1 - Comparison between calculated molar ratio Lu:DOTATATE and 177Lu-DOTATATE radiochemical
purity (%) in two situations: 1) not considering the influence of Hf; 2) considering the influence of Hf.
Conclusion: The data in the Table 1 show that increment in DOTATATE used is due to: 1) the relative
increase in the amount of Lu isotopes; 2) the increase of Hf formed by Lu decay. It suggests that Hf is
an important competitor for DOTATATE binding site. These data are relevant in the synthesis of 177LuDOTATATE with high specific activity.
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
RADIOSYNTHESIS OF CHOLINE LABELLED WITH CARBON-11 AND
PRELIMINARY IMAGING STUDY IN TUMOR MODEL
Marina Bicalho Silveira1, Bruno Melo Mendes1, Danielle Cunha Campos1, Adriana Márcia
Guimarães Rocha1, Soraya Maria Zandim Maciel Dias Ferreira1, Juliana Batista da Silva1
Unidade de Pesquisa e Produção de Radiofármacos (UPPR) - Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/
CNEN), Belo Horizonte, Brazil, [email protected]
1
Positron-emitter-labelled choline analogues have the potential to serve as oncologic probes for molecular
imaging with positron emission tomography (PET). It has been shown that increased uptake of choline occurs
due to increased phospholipid synthesis, which is associated with the high rate of tumor cell proliferation1.
Carbon-11 (11C) is an attractive PET radionuclide since carbon is a ubiquitous element in biomolecules
and labelling with 11C does not change chemical structure and biochemical properties of the compounds.
Choline labelled with carbon-11 (11C-choline) is a promising radiopharmaceutical that has been synthesized
in foreign countries for more than 20 years and is already approved by the FDA for clinical PET imaging
in recurrent prostate cancer2. However, first productions of 11C-choline in Brazil are being held at UPPR/
CDTN. The aim of this work was to synthesize 11C-choline and perform a preliminary imaging study of
tumor in mice. Firstly, 11C-carbon dioxide was produced in a PETtraceTM 16.5 MeV Cyclotron (GE) by
the nuclear reaction 14N(p, α)11C. Then, 11C-carbon dioxide was converted to 11C-methyliodide. Finally,
11
C-choline was prepared using Tracerlab™ FXC PRO (GE) by the 11C-methylation of dimethylamylamine
(DMAE). DMAE (60 μL) was dissolved into 20 μL of ethanol and loaded onto a C18 Sep-Pak cartridge. After
radiolabelling, the final product was purified by washing with ethanol (5 mL) and water (10 mL) through
CM cartridge. Finally, 11C-choline was eluted with saline solution (5 mL). Total synthesis time was about
24 minutes (n=3). Radiochemical purity was determined by HPLC. The non-decay-corrected radiochemical
yield was 13.8±2.0% with radiochemical purity of more than 97%. MicroPET imaging study was performed
using human prostate cancer in the nude mouse xenograft model. Mice were intravenously injected with
11
C-choline 13 ± 7 MBq/100 μL. Images were acquired during 30 minutes while mice were kept anesthetized
by inhalation using isoflurane. The initial dynamic microPET imaging data indicated tumor/muscle ratio of
approximately 1.5 and confirmed increased uptake of 11C-choline in the tumor (0.7 %ID/g), indicating the
relative effectiveness of the radiopharmaceutical. Due to the rapid expansion of PET imaging in clinical
management of patients, 11C-radiotracers hold great promises. The radiosynthesis implemented at UPPR/
CDTN can be used to produce 11C-choline for future preclinical and clinical studies. Reaction conditions are
being optimized in order to obtain higher radiochemical yield. Beyond that, analytical methods are under
development for better quality assessment of the radiopharmaceutical.
REFERENCES
1) T. Hara, N. Kosaka, H. Kishi. J. Nucl. Med. 39 (1998) 990.
2) U.S. Food and Drug Administration, J. Nucl. Med. 53[12] (2012) 11N.
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EFFECT OF ELUENT COMPOSITION ON FINAL STEP OF [18F]FLUOROTHYMIDINE
PRODUCTION AND ITS EFFECTIVENESS IN VITRO
Leonardo Tafas Constantino do Nascimento1, Marina Bicalho Silveira1, Soraya Maria Zandim
Ferreira1, Raquel Gouvea dos Santos1, Juliana Batista da Silva1
Unidade de Pesquisa e Produção de Radiofármacos - Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/ CNEN), Belo
Horizonte, Brazil, [email protected]
1
3’-Deoxy-3’-[18F]fluorothymidine ([18F]FLT) is a radiolabeled imaging agent that has been proposed
for investigating cellular proliferation with Positron Emission Tomography (PET). Clinical studies have
reported this radiopharmaceutical as a promising radiotracer for detection and assessing therapy response
of brain tumor, lung, breast and other types of cancer1. During the past few years, several novel approaches
for [18F]FLT synthesis have been developed, mainly focused on optimization of reaction conditions and
purification methods2. The present study reports the use of two different eluents in the final step of [18F]
FLT production and the evaluation of its effect on radiochemical yield and product quality. An automatic
module Tracerlab™ MXFDG (GE) and the sequence program were adapted for [18F]FLT synthesis. As soon
as dry [18F]fluoride was obtained, 25 mg of the precursor 3′-N-boc-5′-O-DMTr-3′-O-nosyl-lyxothymidine
was added for nucleophilic substitution at 100°C for 5 minutes. After hydrolysis step at 85ºC for 5 minutes,
the mixture was allowed to cool and inserted into PS-H, WAX and HLB cartridges for purification. The
elution (last step) was done through HLB and Alumina cartridges, by two ways. In the first one, 14 mL of
water:ethanol (90:10, v/v) (n=10) were used and in the second, 14 mL of saline:ethanol (92:8, v/v) (n=7),
obtaining two different final formulations of [18F]FLT. The mean of the corrected radiochemical yields
corresponded to 26.0±1.4 % for elution with water and ethanol and to 24.1±2.3 % for elution with saline and
ethanol, which could indicate that the eluent solutions have similar elution strength. Radiochemical purity
of both was higher than 98%. No formulation presented residual acetonitrile or tetrabutylammonium greater
than the adopted limits: 0.04% and 100 µg/mL, respectively. The pH of the final product was equal to 5.3±0.9
and 5.8±0.8 after elution with water and ethanol or with saline and ethanol, respectively. Concentrations
of known byproducts as thymine, thymidine, chlorothymidine and stavudine were determined by HPLC
and all were lower than 0.5 µg/mL, demonstrating no significant difference between the two formulations.
Preliminary in vitro studies showed that thymidine and Chlorothymidine decrease 18FLT cellular uptake,
showing that their concentrations should be monitored. The amount of ethanol was determined by gas
chromatography and it was around 7 % in both formulations. Since satisfactory radiochemical yields were
achieved and both formulations complied with quality requirements, any of the elution procedures could be
performed. However, as reported in literature, radiopharmaceutical preparations containing ethanol should
be preferentially diluted with saline instead of water for injections, as the latter could result in a hypotonic
solution and cause hemolysis3. Therefore, the mixture of saline:ethanol (92:8, v/v) was chosen as the eluent
in the final step of [18F]FLT production in Technology Nuclear Development Center.
REFERENCES
1)L. B. Been, et al. Eur. J. Nucl. Med. Mol. Imaging 31 (2004) 1659.
2)C. Pascali, et al. Nucl. Med. Biol. 39 (2012) 540.
3)K. Serdons, A. Verbruggen and G. Bormans. J. Nucl. Med. 49 (2008) 2070.
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
Determination of gamma emitting radionuclidic impurities of 99Mo
produced by nuclear fission of 235U
Daphne de Souza Said1, Carla Roberta de Barros Rodrigues Dias1, Josiane Zini1, Tânia de Paula
Brambilla1, João Alberto Osso Junior1
Centro de Radiofarmácia, Instituto de Pesquisas Energéticas e Nucleares (IPEN-CNEN/SP), São Paulo, Brazil,
[email protected]
1
Nuclear medicine is a medical modality in which nuclear properties of various radioisotopes are utilized for
diagnosis and therapy of various pathologies. More than 90% of all procedures are diagnostic imaging, and
more than 80% of the images are obtained by using 99mTc, radionuclide supplied by 99Mo/99mTc generators1. The
radionuclide father 99Mo is a fission product of 235U, therefore its chemical separation is extremely complex.
For generators safe use a strict quality control of 99Mo is necessary, including chemical, radionuclidic and
radiochemical purity analysis. For the determination of the radionuclidic purity, the activities of the main
radionuclidic impurities must be quantified, and their values shall not exceed a determinate percentage
of the sample’s total activity (values stated by the Pharmacopoeia2). IPEN-CNEN/SP routinely produces
99
Mo/99mTc generators by importing 99Mo produced by nuclear fission of 235U and today seeks to nationalize
the production of 99Mo at its planned new Brazilian Multipurpose Reactor. The goal of this work is to
identify and quantify the main gamma emitting impurites by gamma spectroscopy. 99Mo samples obtained
by nuclear fission of 235U imported from Argentina, South Africa and Canada were analyzed at a gamma
spectrometer composed of a coaxial HPGe detector, model GX1518, coupled to a multichannel acquisition
system by Canberra Inc., USA. The spectrum obtained by this technique allows qualitative and quantitative
analysis of the sample’s impurities. The preliminary analysis results and the established protocol will be
presented.
REFERENCES
1) J. A. Osso Jr, M. F. Catanoso, G. Barrio, T. P. Brambilla, R. Teodoro, C. R. B. R. Dias, K. N. Suzuki, Curr. Radiopharm. 5
(2012).
2) Ph. Eur. 7.0 (Vol.1) (01/2011) 999.
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INFLUENCE OF HUMIDITY IN THE 99mTc-ECD RADIOCHEMICAL PURITY
Elaine Vasconcelos dos Santos1, Mércia Liane de Oliveira1, Joao Eudes do Nascimento1
Centro Regional de Ciências Nucleares do Nordeste – CRCN/CNEN, Recife, Brazil, [email protected]
1
The main reason to perform stability studies of pharmaceuticals is a concern on public health, since the
degradation of a medicine can lead to the loss of therapeutic efficacy or to the increase of toxicity. The
widespread use of compounds labeled with Technetium-99m (99mTc) in scintigraphy reveals a clear need to
evaluate the stability of radiopharmaceuticals in various conditions, considering intrinsic and extrinsic factors
that can affect the stability of these products.1This study aims to evaluate the effect of relative humidity on the
stability of the radiopharmaceutical 99mTc-ECD by periodic radiochemical purity reviews and pH of samples
stored under conditions of controlled temperature and humidity. Samples of ECD-TEC (Ethyl Cysteinate
Dimer)2, made by IPEN (Nuclear and Energy Research Institute), labeled with injectable solution of sodium
pertechnetate (Na99mTcO4) were evaluated. After the removal of an aliquot for negative control, samples
were stored in a climatic chamber and subjected to 40ºC and minimum relative humidity of 20% and a
maximum of 90%. Additionally, for comparative purposes, samples of 99mTc-Sestamibi radiopharmaceutical
produced by Radiopharmacus, were stored under the same conditions mentioned above. The radiochemical
purity of the samples was analyzed by the thin layer chromatography, using silica-gel aluminum plates and
Whatman paper as stationary phases. The mobile phases used were 20% NaCl and acetone for 99mTc-ECD
and Methanol and 0.9% NaCl for 99mTc-Sestamibi. The samples pH was also evaluated by using pH indicator
paper (2.0 to 9.0) in a scale division of 0.5. Five test points were performed, the first one immediately after
the labeling procedure and the last one, 24 hours after the tracing. In each analysis the sample results were
compared to the negative control.3 Samples of each one of the radiopharmaceuticals were evaluated in parallel
and each one showed a different behavior. Samples of 99mTc-Sestamibi remained stable over 24 hours, with
similar behavior to the negative control. The samples of 99mTc-ECD showed, however, accelerated radiolytic
decomposition profile compared to the negative control. From the results obtained it was concluded that the
radiopharmaceutical 99mTc-ECD is more sensitive to interference from environmental factors and that this
behavior does not characterize a trend for other radiopharmaceuticals labeled with Technetium-99m (99mTc).
No significant changes in pH of both compounds were observed.
REFERENCES
1) E. G. Leite, Estabilidade: importante parâmetro para avaliar a qualidade, segurança e eficácia de fármacos e medicamentos.
Programa de Pós-Graduação em Ciências Farmacêuticas, (2005).
2) I. Zolle, Preparation and Quality Control in Nuclear Medicine (2007) 268.
3) BRASIL. Ministério da Saúde. Agência Nacional de Vigilância Sanitária – ANVISA. Resolução RE nº 01, de 29 de julho de
2005. Guia para realização de estudos de estabilidade. Diário Oficial da União, Brasília, DF, 01 de agosto de 2005.
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SYNTHESIS OF A NOVEL RADIOGALLIUM-PEPTIDE BASED ON DISINTEGRIN
LEUC-B FOR TUMOR TARGETING
Lucilene Marcia Gabriel1, Anayive Perez-Rebolledo1, Daniel M Santos2, Adriano
Monteiro de Castro Pimenta2, Felipe Henrique de Souza Silva1, Eladio F. Sanchez3, Raquel
Gouvea dos Santos1-4
Unit of Radiobiology, Center for Development of Nuclear Technology CDTN/CNEN, 2Federal University of Minas Gerais,
Ezequiel Dias Foundation, 4INCT- Molecular Medicine, Belo Horizonte, Brazil, [email protected]
1
3
Integrins regulate several cellular functions crucial to the initiation, progression and metastasis of solid
tumors. Thus, they become an interesting target for the development of agents for cancer therapy and
diagnosis. The disintegrin Leucurolysin-B (leuc-B) isolated from Bothrops leucurus venom possesses an
ECD-domain able to bind to cell surface integrins and promote the inhibition of cell adhesion altering the
properties of extracellular matrix (ECM) proteins, which play a central role in metastasis and angiogenesis.
In previous report it was demonstrated that Leuc-B has potent cytotoxic effect in a micromolar range against
tumor cell lines studied1. Recently we built a small peptide based on Leuc-B, Leuc-B-peptide1(L1), which
showed by molecular modeling strategy increased integrin interaction efficiency (Gold score 79.27) and
therapeutic potential against malignant gliomas. The aims of this work were to synthesize a 67Ga-radiolabelled
analog of L1 coupled to DOTA, 67Ga-DOTA-L1, and evaluate its specificity towards malignant tumors
expressing αvβ3 integrins. DOTA-L1 was obtained by Solid Phase Peptide Synthesis using 0.82 to 0.89 mCi
of GaCl3 in ammonium acetate buffer (NH4OAc). Two conditions of heating, 30 min at 75ºC or 10 min at
90ºC, were evaluated. The reaction mixture was purified by C18 Sep-Pak cartridges and the final product
was obtained in MeOH. natGa-DOTA-L1 was used as a reference standard. Thin-layer chromatography on
aluminum plates (Merck) was used for radiochemical purity (RCP) evaluation. The radio-chemical yields
(RCY) were corrected for decay and referred to the radioactivity of 67Ga-DOTA-L1 at the end of synthesis
with respect to the total 67Ga activity used. MALDI-MS spectra confirmed the stability of the radiolabelled
product. The specificity of the new radiotracer 67Ga-DOTA-L1 was assessed by in-vitro cell binding studies
in the absence or presence of a 1000 fold the native peptide. 67Ga-DOTA-L1 was obtained with a RCY
around 78.2% which showed a strong dependence on the purification process by solid phase extraction.
The RCP was around 84.4% and the specific activity 3.7-11.9 GBq/μmol. 67Ga-DOTA-L1 bound to tumor
cells with high specificity (55% in breast cancer MCF7 cells and 66% in glioma U87 cells). Cyclo(RGDyK)
inhibited completely the specific binding of 67Ga-DOTA-L1 on tumor cells. In summary, 67Ga-DOTA-L1
was produced with good specific activity and high specificity for tumors expressing αvβ3 integrins and may
constitute a platform for development of imaging agent against metastatic tumors.
REFERENCES
1) L. M. Gabriel, E. F. Sanchez, S. G. Silva, R. G. Santos, J Venom Anim Toxins incl Trop Dis, 18 (2012) 24
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Radiation Protection
4th-INCC 2014 I 4th International Nuclear Chemistry Congress
CESIUM-137 CONTENT IN MILK - MONITORING AFTER FUKUSHIMA NUCLEAR
POWER PLANT ACCIDENT
Flavia Groppi1, Simone Manenti1, Mauro L. Bonardi1, Luigi Gini1, Alexandra Ioannidou2
Università degli Studi di Milano & INFN, Physics Department – LASA Laboratory, 2Aristotele University, Physics Department,
Segrate (MI), Italy, [email protected]
1
Radionuclides released during an accident can be transported over long distances, before they are deposited
by fallout on vegetation and soil. Such an event occurred after the Chernobyl accident in April 1986 where
extensive fallout of various long- and short lived radionuclides was observable in many European countries,
including Italy. The resulting contamination of the vegetation has decreased due to radioactive decay and
weathering. Longer lived radionuclides, however, are still present in the soil and are taken up by plants via
their roots. In particular 137Cs that is one of the most important contaminants because of its long half life,
affinity for biological system and its uptake to man through diet.
In March 2011 Fukushima accident contributed with new input in the atmosphere of contaminants: a
cloud containing radioactivity was formed in air over Fukushima nuclear power plant NPP, moved over
the Pacific Ocean in the direction of the Arctic Ocean, enter in the Atlantic Ocean and diffused over the
European continent. The transferred radioactivity was detectable all over the word: many laboratories started
measurements and presented results on the fallout from the Fukushima nuclear accident1. Also in Italy
were made a series of measurements of the fission product radionuclides in different regions and places. In
particular our research group was focused on measurements of radioactivity present in air, water, snow, soil,
grass and milk in Milano and Monte Rosa region2.
In fresh goat and cow milk produced and collected in a farm at a village in Anzasca valley near Macugnaga
(rural area), in Monte Rosa mountain at 500 m height in the period April to July 2011 were found small
values of concentration of 131I and 137Cs. The 134Cs/137Cs activity ratios can reveal information on radioisotope
origin. The relative high activity concentrations of 137Cs and the very low values of the activity ratio of
134
Cs/137Cs, in combination with the absence of 134Cs in most of the cases indicate a strong contribution
from “older” 137Cs, probably from the Chernobyl accident and past global fallout and not from Fukushima
accident. After these preliminary results we start on January 2013 a campaign in order to continue to monitor
this area and have some reference data of radiocaesium concentration level due to different fallouts. Some
measurements were conducted in order to to find a correlation between the 137Cs concentration values and
the animals pasture and environments which are utilized for food production (due to the pathway: fodderanimalmilk). Finally the results of the two time series of collected data will be presented and discussed with
some considerations dealing with the effects on the public health.
REFERENCES
1) P. Thakur, S. Ballard, R. Nelson, Sci. Tot. Environ.458 (2013) 577.
2) A. Ioannidou, S. Manenti, L. Gini, F. Groppi, J Environ Radioact 114 (2012) 119.
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COMPARISON BETWEEN LM-OSL AND CW-OSL APPLIED TO IONIZING
RADIATION DOSIMETRY
René Rojas Rocca1, Sonia Hatsue Tatumi1
Sao Paulo Federal University UNIFESP, Santos, Brazil, [email protected]
1
Optical Stimulated Luminescence (OSL) is broadly used to obtain accumulated dose (AD) in quartz crystals,
usually using a continuous wave (CW) stimulation; it means to stimulate the crystal with continuous blue
light (same intensity during all the measurements) and recording OSL decay curve, which consist the UV
emission of the crystal with time; AD is evaluated from calibrated OSL growth curve with dose, obtained by
using the initial part of the OSL decay curves.
However, we can also use a different mode of stimulation where the stimulation intensity increase linearly
with the time, this technique is termed Linear Modulation Optical Stimulated Luminescence (LM-OSL)
[1]. The experimental LM-OSL curve show peaks of the emissions with the time, until all the related traps
were emptied, at which point the OSL intensity decays to zero. Usually, the stimulation intensity is linearly
increased from 0 and 80 mW/cm2 [2], during this process the emission intensity is recorded and it is not
more a decay curve, and it can be observe many contributions from the various traps deeps, divided in fast,
medium and long components contributions, which are not clear in CW-OSL results. The LM-OSL curve
shows peaks similar to those of the Thermoluminescence glow curve.
In the present work two techniques LM and CW-OSL were used to determine AD in natural quartz crystal
and the LM-OSL results approved about 5-10% more aliquots than CW-OSL, it was used the second peak
(medium component) in the analyses. The results of AD values are similar to those obtained by CW-OSL
and presented minor uncertainty in the results.
REFERENCES
1) C. K. Kuhns, N. Agersnap Larsen, S.W.S. McKeever, Radiation Measurements 32 (2000) 413.
2) L. Botter-Jensen, C. E. Andersen, G. A. T. Duller and A. S. Murray, Radiation Measurements 37 (2003) 535.
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4th-INCC 2014 I 4th International Nuclear Chemistry Congress
A FEMALE VOXEL PHANTOM FOR RADIOPHARMACEUTICALS INTERNAL
DOSIMETRY
Bruno Melo Mendes1-2, Iassudara Garcia de Almeida2, Bruno Machado Trindade2, Tarcísio
Passos Ribeiro de Campos2
Centro de desenvolvimento da Tecnologia Nuclear – CDTN/CNEN – Campus UFMG, 2Universidade Federal de Minas Gerais
– UFMG, Departamento de Engenharia Nuclear - NRI – Campus UFMG, Belo Horizonte, Brazil, [email protected]
1
Introduction. Conventional radiopharmaceutical’s dosimetry is based on standardized analytical shape
models and homogeneous uptake, following the MIRD formalism. The MIRD method provides estimations
of the average absorbed doses in each organ and the effective dose, suitable for stochastic effect analysis.
Voxel’s models, in turn, allow setting up the spatial distribution of doses, histogram dose versus volume, as
well as average dose in interest organs, requirement to any deterministic and stochastic effect analysis. In
this way, voxel´s models can provide more comprehensive and complex dosimetric data than the standard
analytical models. This study aimed the development of a computational voxel’s female phantom for MCNP
transport code - Los Alamos National Laboratory.
Methodology. The voxel model was based on images from Visible Human Project® - female specimen available on the internet. Transversal cross sections from the top of the head to the base of abdomen spaced
ten millimeters were utilized. Each slice was divided into a 10 x 10 mm grid. The resulting resolution was
10x10x10 mm. The model assembly, tissue recognition and MCNP format exportation were performed by
SISCODES in house software. The organ/tissue elemental composition and density were obtained from
ICRU-46 and ICRP-89. Some organ volumes were adjusted to match to the reference woman.
Results and Discussion. Figure 1A presents the female analytical model traditionally employed for
radiopharmaceutical’s dosimetry. Figures 1B, 1C and 1D shows respectively coronal cross section, sagittal
cross section and 3D representation of the namely NRI woman phantom developed. Note that the organ’s
anatomy in voxel’s model is well delineated than the observed on the analytical model. The organ masses in
voxel’s model presented an average error of 1% in comparison with ‘reference woman’ (ICRP-89). However,
fluctuations up to 40% were observed in specific small organs. This fact results from internal individual
anatomical differences and especially from distinct tissue’s density employed, among other reasons.
Conclusions. The NRI-phantom shows better anatomical consistency than the female analytical model.
Besides the averaged absorbed doses per organ and effective dose estimates for new radiopharmaceuticals,
the evaluation of maximum and minimum dose values in each organ and the dose spatial distribution will
be possible to be estimated. The contribution and usefulness of MIRD method for radiopharmaceutical’s
dosimetry is undeniable, however voxel’s models can add new information to existing studies.
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
GAMMA EXPOSURE DUE TO BUILDING MATERIALS IN A RESIDENTIAL
BUILDING AT PERUÍBE, SÃO PAULO, BRAZIL
Camila Dias Cazula1, Marcia Pires de Campos1, Barbara P. MAZZILLI1
Instituto de Pesquisas Energéticas e Nucleares, São Paulo, Brazil, [email protected]
1
Radionuclides present in the Earth´s crust contribute to the population radiation exposure. According to
the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR, 2000), this
contribution corresponds to 84% of the average worldwide radiation exposure (2.4 mSv y-1). The radon is
responsible for 53% of this contribution, whereas the others radionuclides of the U and Th series correspond
to 17% and K-40 to 14%. Therefore, the gamma external exposure to the population due to the radionuclides
present in the Earth’s crust correspond to 29% of the total exposure.
It is well known that most building materials contain traces of natural radionuclides. Materials derived
from rock and soils contain mainly natural radionuclides of the uranium (238U) and thorium (232Th) series
and the radioactive isotope of potassium (40K). In the uranium series, the decay chain segment starting
from radium (226Ra) is of radiological concern and, therefore, is often considered instead of uranium. The
worldwide average concentrations of radium, thorium and potassium in the earth’s crust are about 35 Bq/kg,
35 Bq/kg and 400 Bq/kg, respectively. Exposure in the interior of dwellings depends on the concentration
of the building material and soil beneath the building. Within multi storey buildings, the contribution of
radionuclides from the soil to the indoor gamma exposure is relevant on the basement and ground floor,
whereas in the upper floors the main contribution is due to building materials.
The aim of this study is to determine the concentration of 226Ra, 232Th and 40K in the soil and building
materials in a multi storey building. These results will be used to evaluate the activity concentration index
(ACI) and the external gamma exposure for dwellers, in order estimate the contribution of the soil and
building materials.
REFERENCES
1)M.P. Campos, B.R.S. Pecequilo. Rev. Bras. Pesq. Des. 5(2) (2003) 60.
2)United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR). Sources and effects of ionizing
radiation. Vol. 1 (2000)
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Estimation of Radiation Risks to Patients and occupational
exposure in Pacemaker Interventional Procedures
Khalid S. Alzimami1, Islam Hassan2, Abdelmoneim Sulieman3
Radiological Sciences Department, College of Applied Medical Sciences, King Saud University, 2Salman bin Abdulaziz University,
College of Applied Medical Sciences, Radiology and Medical Imaging Department 3Basic Science Department, College of Medical
Radiologic Sciences, Sudan University of Science and Technology, Riyadh, Saudi Arabia, [email protected]
1
Abstract
Pacemakers procedures are performed using fluoroscopy reduce patient morbidity and mortality compared
to operative procedures. These procedures require radiation exposure to patients and physicians. The
objectives of the present quantify the patient entrance skin air kerma dose (ESAKs) during cardiac pacemaker
procedure, estimate the patient effective dose and cancer risks and to compare the dose received by patient
during cardiac pacemaker in Sudan with the standard dose reference levels.
A total of 45 patients undergoing five different pacemaker implantation procedure two hospitals were
assessed. Patient’s demographic data, exposure parameters for both fluoroscopy and radiography were
quantified. ESAK was measured using thermo luminescence dosimeters (TLD-GR200A: LiF: Mg, Cu, P
(FIMEL, Freance))). TLDs were calibrated under reproducible reference conditions. Patients ESAKs were
quantified using mathematical equation based on patient exposure factors. Effective doses were estimated
using software based on Monte Carlo simulation from National Radiological Protection Board (NRPB). The
effective dose values were used to estimate the cancer risk from pacemaker procedure.
The range of patient doses during pacemaker procedures was from 28.80 mGy per procedure to 2020.60 mGy
per procedure. Strong Linear relation was found between fluoroscopy dose and fluoroscopy time (R2 =1).
The patient doses reached the doses for skin erythema doses and increase the probability of cancer risks. The
radiation dose values are higher compared with recent literature. Staff doses are well below the annual dose
limits. Reduction of patient doses is a prime importance and practitioners should optimize the radiation
dose for further dose reduction without compromising the diagnostic and therapeutic finding.
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BACKWARD DOSIMETRY USING GREEN QUARTZ AND A FEW VARIETY OF
SILICATE MINERALS
Shigueo Watanabe1, Nilo Francisco Cano Mamani2, Renata de Faria Barbosa2, T. K. Gundu
Rao1
Institute of Phyics, University of São Paulo, 2Federal University of São Paulo, Santos, Brazil, [email protected]
1
In the usual TL (Thermoluminescence) radiation dosimetry, TL intensity is measured as function of radiation
dose. The common feature of this dependence is that the TL or EPR (Electron Paramagnetic Resonance)
intensity increases with the dose, linearly in the low dose region. It can be used in radiation dosimetry and is
an example of forward dosimetry. A sample irradiated with 300 Gy gamma-rays (remember that E1´-center
EPR is saturated at this dose value) was divided into several portions, each one irradiated to radiation dose
varying from low value up to 500 Gy. The Fig. 1 presents the EPR intensity of E1´-center as function of dose.
This result can, therefore, be used as radiation dosimetry; we call it Backward dosimetry.
We have carried out similar measurements on three varieties of beryl: morganite (pink), goshenite (uncolored)
and aquamarine (greenish blue) using, however, TL instead of EPR. The radiation dose response of several
minerals, including green quartz, have shown that the TL intensity or ESR intensity decreases with doses
ranging from low to high dose. This decrease is observed after the minerals are subjected to pre-irradiation
to high doses in the range of kGy. Such minerals have the potential to be used in dosimetry. Fig.nformation
to existing studies
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MONITORING OF ENDS WORKERS EXPOSED POSITRON EMITTERS
Natalia Cassia do Espirito Santo Nascimento1, Êudice Correia Vilela1, Mércia Liane de
Oliveira1
Centro Regional de Ciências Nucleares do Nordeste, Recife, Brazil, [email protected]
1
The increasing amount of applications using non-sealed positron-emitting sources requires the completion
of a thorough dosimetric monitoring of workers exposed to these types of radiation. These exposures occur
principally in the fingers and hands, because these are body parts that are in direct contact or very close to
the radiation source. This paper aims establishing a methodology for calibration of extremities dosimeters
based LiF: Mg, Ti (TLD-100) for use in mixed beams of radiation. For this, we used the dosimetric system
XD EXT-RAD-100, manufactured by Harshaw (now Thermo Scientific). The dosimeters were irradiated
on acrylic phantom finger. In order to analyze the performance of the dosimetric system used, tests were
made with individual sensitivity, batch homogeneity, reproducibility, beta and photon energy response and
angular response, according to the recommendations of ISO 12794. Subsequently, the dosimeters were
calibrated in standard beams of beta radiation (using a source of 90Sr +90Y) and gamma (using a source
of 137Cs). The calibration of the dosimeters was carried in terms of Hp (0.07). To simulate the working
environment of monitored individuals, tests were carried out in mixed radiation fields with sources of 137Cs
and 90Sr/90Y to choose what the best calibration factor for the dosimetric system EXT-RAD-100 XD. The
batch of dosimeters used in this study showed a value of homogeneity better than 6.9% and reproducibility
better than 4.8%. The study of angular response of the dosimeters showed acceptable variation of the
response (less than 15%), demonstrating its utility for dosimetry of extremities. The test of beta and photon
energy response also presented according to ISO 12794, because the variation of TL response was less than
50% in the whole energy range considered. The results for tests carried out in mixed radiation beta-photon
fields suggest that for use of extremity dosimeters EXT-RAD XD-100 type in mixed fields of beta-radiation
photons, the most appropriate calibration factor is the 137Cs. Considering these results, we can conclude that
the EXT-RAD XD-100 dosimetric system meets the necessary requirements for application in monitoring
the ends of individuals occupationally exposed to mixed radiation beta-photon fields.
Keywords: dosimetry of extremities; calibration of dosimeters; mixed radiation fields.
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Nuclear and Related Techniques
4th-INCC 2014 I 4th International Nuclear Chemistry Congress
BIOMONITORING OF ESSENTIAL CHEMICAL ELEMENTS USING TERRESTRIAL
MOLLUSKS L. ANGULIFERA OF PERNAMBUCO MANGROVES
Julyanne T. B. MÉLO1, Rebeca S. CANTINHA1, Ana M. M. A. MELO2, Marcelo R. L. MAGALHÃES1,
Emerson E. G. FARIAS1, Alesxandro F. NASCIMENTO1, Elvis J. FRANÇA1
Divisão de Pesquisa e Desenvolvimento – DIPED, Centro Regional de Ciências Nucleares do Nordeste – CRCN/NE, Comissão
Nacional de Energia Nuclear – CNEN, Recife, PE, Brazil. [email protected] 2Departamento de Biofísica e Radiobiologia,
Universidade Federal de Pernambuco, 1235, Recife, PE, Brazil.
1
Essential chemical elements are not frequently monitored in Brazilian ecosystems, mainly for mangrove
invertebrate compartment. These productive costal areas are of utmost relevance for guaranteeing the
environmental integrity. The terrestrial mollusk Littoraria angulifera (Lamarck, 1822) is quite abundant
in Brazilian mangroves, however, no information on the essential chemical element distribution for this
terrestrial mollusk could be found in the literature. Therefore, this study aimed to monitor chemical
elements in L. angulifera from four mangroves of the Pernambuco State, Brazil. The mangrove mollusks
were sampled (N = 27) in areas presenting different degrees of conservation. Energy dispersive X-ray
fluorescence (EDXRF) and flame atomic absorption spectrometry (FAAS) were applied to determine the
mass fractions of Cl, Fe, K, Mg, Mn and P in the animals. In the laboratory, the animals were subjected
to low temperature and, after induced euthanasia, shells were removed. Tissues were freeze-dried for 48
hours and manually milled by means of porcelain mortar. For EDXRF, test portions and reference materials
were directly analyzed in Shimadzu equipment, model EDX-720, using vacuum atmosphere, for the
determination of Cl, Fe and P. Potassium, magnesium and manganese were analyzed by FAAS, model
SpectrAA200, after nitric-perchloric chemical sample preparation in microwave equipment. There were not
observed significant variations of K mass fractions at the 95% confidence level in animals from the different
areas. Iron and phosphorus were increased in region with high environmental impacts (urban mangrove of
Olinda Municipality), while mollusk magnesium and manganese mass fractions decreased substantially. For
chlorine, the highest concentrations were observed in the most preserved area (Rio Formoso Municipality).
Results indicated a clear accumulation pattern of Fe, Mg, Mn and P according to the environmental impacts.
As a consequence, this snail could be used as biomonitor of environmental quality for essential chemical
elements in Brazilian Northeast mangroves.
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SUMMARY OF AUTHORS
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ADDED, NEMITALA............................................................................................................................................................... 150
ALARCÓN, ALBERTO FERNÁNDEZ............................................................................................................................. 72; 241
ALBERTI, HEBER LUIZ CAPONI.................................................................................................................................. 299; 300
ALBUQUERQUE, CAROLINE RODRIGUES......................................................................................................................... 91
ALENCAR, MARCOS MEDRADO DE.......................................................................................................................... 198; 232
ALIEV, RAMIZ A................................................................................................................................................................. 65; 67
ALKHORAYEF, M............................................................................................................................................................ 287; 288
AL-MALKI, YOUSIF............................................................................................................................................................... 109
ALMEIDA, ANA SOFIA.......................................................................................................................................................... 177
ALMEIDA, EDUARDO DE..................................................................................................................................................... 256
ALMEIDA, GEVALDO L........................................................................................................................................................... 85
ALMEIDA, IASSUDARA GARCIA DE.................................................................................................................................. 317
ALMEIDA, MARIA CANDIDA MOREIRA DE..................................................................................................................... 143
AL-QAHTANI, MOHAMMED................................................................................................................................................ 109
ÁLVAREZ, ALFREDO MONTERO........................................................................................................................................... 89
ÁLVAREZ, JUAN REINALDO ESTEVEZ................................................................................................................................ 89
ÁLVAREZ, ROMÁN PADILLA................................................................................................................................................. 89
ALVES, R. N............................................................................................................................................................................. 143
ALZIMAMI, KHALID S........................................................................................................................................................... 319
AMARAL, ROMILTON DOS SANTOS.................................................................................................................................. 194
AMBROGI, JÉSSICA BRAGA................................................................................................................................................. 152
AMORIM, TATIANE P............................................................................................................................................................. 296
ANDREOLI, MARCO.............................................................................................................................................................. 267
ANJOS, MARCELINO JOSÉ DOS.......................................................................................................................... 240; 260; 261
ANTONIO, AMILCAR LOPES................................................................................................................................ 151; 184; 186
ANTUNES, RENATO ALTOBELLI................................................................................................................................. 163; 164
ANZELLOTTI, ATILIO I.......................................................................................................................................................... 209
AONO, TETSUO....................................................................................................................................................................... 104
ARAE, HIDEKI......................................................................................................................................................................... 104
ARAÚJO, ANDRÉ LUIS LIMA DE................................................................................................................... 73; 106; 195; 298
ARAUJO, ASTOLFO G. M....................................................................................................................................................... 153
ARAÚJO, EDVAL GONÇALVES DE...................................................................................................................................... 163
ARAÚJO, UBIRATAN BARBOSA DE.................................................................................................................................... 261
ARAÚJO, WANDERSON S..................................................................................................................................................... 296
ARI, KADIR...............................................................................................................................................................................111
ARINE, BRUNO BURINI ROBLES................................................................................................................................ 106; 195
ARMELIN, MARIA JOSÉ A.................................................................................................................................................... 173
ASAI, M....................................................................................................................................................................................... 66
AVCIBASI, NESIBE................................................................................................................................................................. 207
AVCIBASI, UGUR............................................................................................................................................................ 207; 208
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AVEGLIANO, ROSEANE PAGLIARO........................................................................................................................... 152; 231
AVINO, PASQUALE................................................................................................................................................................. 105
BACCHI, MÁRCIO ARRUDA...........................................................................................73; 239; 256; 257; 262; 263; 264; 298
BACCOLO, GIOVANNI..................................................................................................................................................... 58; 277
BAEZ, ERNESTO MARTÍNEZ................................................................................................................................................ 138
BAIK, MIN HOON................................................................................................................................................................... 197
BAILEY, JIM............................................................................................................................................................................. 209
BAKULE, P. B........................................................................................................................................................................... 228
BARBOSA, RENATA DE FARIA..................................................................................................................................... 258; 320
BARBOSA, RODRIGO APARECIDO..................................................................................................................................... 139
BARIŠIĆ, DELKO.................................................................................................................................................................... 193
BARREIRA, JACQUELINE SALES................................................................................................................................ 217; 218
BARREIRA, JOÃO C. M.......................................................................................................................................................... 185
BARROS, LILLIAN.......................................................................................................................................................... 185; 186
BARROS, LILLIAN BOUÇADA DE....................................................................................................................................... 184
BARTONÍČEK, BOHUMIL...................................................................................................................................................... 283
BATISTA, ALZIR AZEVEDO.................................................................................................................................................. 246
BATISTA, JORGE GABRIEL DOS SANTOS................................................................................................................. 183; 210
BATISTA, JORGE L................................................................................................................................................................. 138
BAUMGARDT, DAIANE......................................................................................................................................................... 199
BAZANTE-YAMAGUISHI, RENATA..................................................................................................................................... 286
BAZZOCCHI, ANNA................................................................................................................................................................. 61
BELLIDO, ALFREDO VICTOR BERNEDO............................................................................................................... 84; 85; 203
BELLIDO, LUIS FERNANDO........................................................................................................................................... 84; 203
BELO, LUIZ CLÁUDIO MOURA........................................................................................................................................... 204
BENNETT, JOHN W................................................................................................................................................................... 33
BENTO, ALBINO..................................................................................................................................................................... 151
BERGAMINI, GIOVANI.................................................................................................................................................. 229; 231
BESSONOV, ALEXEI A................................................................................................................................... 129; 131; 133; 134
BHONSLE, UDAY...................................................................................................................................................................... 34
BIGUZZI, FELIPE A................................................................................................................................................................... 73
BLANCO-GONZÁLEZ, ALEJANDRO................................................................................................................................... 206
BOBROWSKI, KRZYSZTOF.................................................................................................................................................... 78
BODE, PETER.................................................................................................................................................................. 239; 264
BOJANOWSKA-CZAJKA, ANNA............................................................................................................................................ 78
BOMBUSE, DENNYS LEYVA.................................................................................................................................................. 89
BONARDI, MAURO L....................................................................................................................................................... 61; 315
BONFIM, SARAH ANDRESA................................................................................................................................................. 146
BONTURIM, EVERTON.......................................................................................................................................................... 137
BOSCARO, MATEUS EUGÊNIO.................................................................................................................................... 262; 264
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BOTELHO, M. LUISA.............................................................................................................................................................. 151
BRAMBILLA, TÂNIA DE PAULA.......................................................................................................................................... 310
BRANDÃO JUNIOR, FRANCISCO ANTONIO..................................................................................................................... 141
CABALKA, MARTIN............................................................................................................................................................... 283
CALDEIRA FILHO, JOSÉ DE SOUZA................................................................................................................................... 307
CAMPOS, DANIELLE CUNHA.............................................................................................................................................. 308
CAMPOS, GUSTAVO LOBATO.............................................................................................................................................. 159
CAMPOS, MARCIA PIRES DE............................................................................................................................................... 318
CAMPOS, TARCÍSIO PASSOS RIBEIRO DE................................................................................155; 156; 159; 219; 230; 317
CANELLAS, CATARINE G. L................................................................................................................................................. 240
CANESIN, FATIMA P............................................................................................................................................................... 203
CANTINHA, REBECA DA SILVA...........................................................................................................103; 172; 247; 248; 253
CAPANNESI, GERALDO........................................................................................................................................................ 105
CARAMITU, ALINA RUXANDRA........................................................................................................................................... 80
CARBOL, PAUL......................................................................................................................................................................... 90
CARBONARI, ARTUR W......................................................................................................................................................... 237
CARDOSO, ELIZABETH CARVALHO LEITE.............................................................................................................. 187; 188
CARMO, ANDRIUS MARCEL JOVENTINO DO.................................................................................................. 245; 252; 254
CARNAVAL, JOÃO PAULO RODRIGUES............................................................................................................................ 139
CARNEIRO, REGINA CÉLIA GORNI...................................................................................................................................... 35
CARVALHO, ANA M.............................................................................................................................................................. 184
CARVALHO, ELITA FONTENELE URANO DE..................................................................................................................... 79
CARVALHO, RENATA R......................................................................................................................................................... 296
CASTILLO, TRINIDAD MARTÍNEZ...............................................................................................72; 169; 196; 241; 293; 294
CASTRO, ANDRE LIMA DE SOUZA..................................................................................................................................... 219
CASTRO, LILIANA.................................................................................................................................................................. 149
CASTRO, LUCAS M........................................................................................................................................................ 160; 199
CATANOSO, MARCELA FORLI..............................................................................................................................................211
CAVALCANTE, FABIO H. M.................................................................................................................................................. 237
CAZULA, CAMILA DIAS....................................................................................................................................................... 318
ČERNE, MARKO....................................................................................................................................................................... 83
CHARUSHNIKOVA, I. A......................................................................................................................................................... 133
CHATT, AMARES.............................................................................................................................................................. 36; 170
CHÁVEZ, ALEJANDRO RAMÍREZ....................................................................................................................................... 294
CHEBERLE, LUAN TEIXEIRA VIEIRA........................................................................................................................ 229; 231
CHIBA, RUBENS..................................................................................................................................................................... 267
CHIN, MARY PIK WAI.............................................................................................................................................................. 99
CHO, SOO YOUNG.................................................................................................................................................................. 191
CHOI, GEUN-SIK..................................................................................................................................................................... 276
CHUNG, DONG-YONG............................................................................................................................................................117
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CHUNG, KUN HO.................................................................................................................................................................... 276
CHVÁTIL, DAVID.................................................................................................................................................................... 273
CLEMENZA, MASSIMILIANO........................................................................................................................................ 58; 277
CORREA, OLANDIR VERCINO............................................................................................................................. 163; 164; 237
COSTA, ANA CRISTINA MORAES DA................................................................................................................................. 261
COSTA, ANA R. P..................................................................................................................................................................... 177
COSTA, ANTONELLA LOMBARDI....................................................................................................................................... 141
COSTA, DIOGO RIBEIRO....................................................................................................................................................... 139
COSTA, GABRIELA DE JESUS LUSTOZA........................................................................................................................... 272
COTRIM, MARYCEL ELENA BARBOZA....................................................................................................................... 79; 295
COZZOLINO, SILVIA MARIA FRANCISCATO.................................................................................................................... 173
CRAPEZ, MIRIAN ARAUJO CARLOS............................................................................................................................ 84; 203
CRISTIANO, BÁRBARA FERNANDES GONÇALVES........................................................................................................ 140
CRUZ, PAULO ALBERTO LIMA DA....................................................................................................................... 50; 148; 306
DAMATTO, SANDRA REGINA.............................................................................................................................. 124; 198; 199
DELGADO, JOSÉ UBIRATAN................................................................................................................................ 140; 143; 306
DELMONTE, BARBARA.................................................................................................................................................. 58; 277
DEMIROĞLU, HASAN.................................................................................................................................................... 207; 208
DIAS, CARLA ROBERTA DE BARROS RODRIGUES......................................................................................................... 310
DIAS, FÁBIO CORDEIRO....................................................................................................................................................... 140
DIAS, PEDRO L. S................................................................................................................................................................... 296
DÍAZ, BRENDA BEATRIZ ESTAÑOL.................................................................................................................................... 293
DOMINGOS, MARISA............................................................................................................................................................... 91
DOMÍNGUEZ, JUDITH........................................................................................................................................................... 138
DOSTÁLEK, PAVEL................................................................................................................................................................. 273
DUCAT-PAGES, LUIS.............................................................................................................................................................. 206
DURAZZO, MICHELANGELO............................................................................................................................................... 171
EFE, HANDE............................................................................................................................................................................ 207
ELIAS, CAMILA....................................................................................................................................................................... 239
ENZWEILER, JACINTA.......................................................................................................................................................... 142
EPPICH, GARY RICHARD........................................................................................................................................................ 57
ERMOLAEV, STANISLAV V............................................................................................................................................... 65; 67
ESPINOSA, GUILLERMO....................................................................................................................................................... 169
ESTRADA, J. S......................................................................................................................................................................... 143
EZEQUIEL, FRANCIOLE JOSÉ.............................................................................................................................................. 139
FABIANO, KAREN CAMPOS................................................................................................................................................. 259
FAGUNDES, ROSANE CORREA........................................................................................................................................... 106
FALCÃO, PATRÍCIA................................................................................................................................................................ 230
FAMĚRA, OLDŘICH............................................................................................................................................................... 273
FARIAS, EMERSON EMILIANO GUALBERTO DE........................................... 233; 245; 252; 253; 254; 278; 279; 280; 285
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FÁVARO, DÉBORAH I. T........................................................................................................................................ 160; 199; 242
FEDOSSEEV, A. M........................................................................................................................................................... 133; 134
FELKLOVÁ, VERONIKA........................................................................................................................................................ 305
FERGUSON, DOUG................................................................................................................................................................. 209
FERNANDES, ELISABETE A. DE NADAI.............73; 103; 172; 239; 245; 247; 248; 250; 251; 256; 257; 262; 263; 264; 298
FERNÁNDEZ, ZAHILY HERRERO.......................................................................................................................................... 89
FERRAZ, ISRAEL ELIAS........................................................................................................................................................ 274
FERREIRA ISABEL C. F. R............................................................................................................................ 151; 184; 185; 186
FERREIRA, ADEMAR DE OLIVEIRA................................................................................................................................... 216
FERREIRA, CLÁUDIA ALVES............................................................................................................................................... 175
FERREIRA, FERNANDA JOSÉ AUGUSTO........................................................................................................................... 146
FERREIRA, MARCELO TARQUÍNIO............................................................................................................................ 229; 231
FERREIRA, PAULO ALVES DE LIMA........................................................................................................................... 116; 192
FERREIRA, SORAYA MARIA ZANDIM........................................................................................................................ 308; 309
FIGUEIRA, RUBENS CESAR LOPES...................................................................................................................... 91; 116; 192
FIGUEIREDO, ANA MARIA GRACIANO............................................................................................................... 91; 142; 238
FLEMING, DONALD G........................................................................................................................................................... 228
FLEMING, PETER MARSHAL....................................................................................................................................... 299; 300
FONSECA, ANA CAROLINA MOREIRA.............................................................................................................................. 183
FONSECA, FELIPE YAMADA........................................................................................................................................ 250; 251
FONSECA, LEANDRO MILHOMENS DA............................................................................................................................ 145
FRAGOSO, MARIA DA CONCEIÇÃO DE FARIAS.............................................................................................................. 233
FRANÇA, ELVIS JOACIR DE................................103; 172; 233; 245; 247; 248; 250; 251; 252; 253; 254; 278; 279; 280; 285
FRANKE, KARSTEN............................................................................................................................................................... 227
FRANKLIN, ROBSON LEOCADIO........................................................................................................................................ 242
FREITAS, MARIA DO CARMO.............................................................................................................................................. 177
GABRIEL, LUCILENE MARCIA............................................................................................................................................ 312
GALINHA, CATARINA ISABEL ALVES LOURENÇO......................................................................................................... 177
GALVÃO, IZABELA................................................................................................................................................................ 205
GARCÍA-TENORIO, RAFAEL.................................................................................................................................................. 37
GARRETT, B. C........................................................................................................................................................................ 228
GAZINEU, MARIA HELENA PARANHUS.................................................................................................................... 278; 285
GENEZINI, FREDERICO ANTONIO......................................................................................................144; 150; 176; 238; 249
GENNARI, ROSELI FERNANDES......................................................................................................................................... 258
GERALDO, ÁUREA BEATRIZ CERQUEIRA........................................................................................................................ 286
GINI, LUIGI........................................................................................................................................................................ 61; 315
GODOY, ANA LUCIA EXNER.................................................................................................................................................. 79
GÖKMEN, ALI............................................................................................................................................................................ 98
GÖKMEN, INCI.......................................................................................................................................................................... 98
GOLZARRI, JOSE-IGNACIO.................................................................................................................................................. 169
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GOMES, TATIANA CRISTINA BOMFIM.............................................................................................................................. 158
GOMIDE, RICARDO GONÇALVES....................................................................................................................................... 274
GONÇALVES, RODOLFO DANIEL MORENO REIS........................................................................................................... 165
GONÇALVEZ, KÁTIA ALESSANDRA.................................................................................................................................... 97
GONZAGA, CLÁUDIO LUÍS.................................................................................................................................................. 256
GONZÁLEZ, IVÁN PUPO......................................................................................................................................................... 89
GONZÁLEZ, MAYDEL RODRÍGUEZ..................................................................................................................................... 89
GONZALEZ, PEDRO............................................................................................................................................................... 294
GORBACHEVA, MARGARITA P............................................................................................................................................ 128
GRAHEK, ŽELJKO.................................................................................................................................................................. 182
GROPPI, FLAVIA............................................................................................................................................................... 61; 315
GRUND, MARCOS SODRE.................................................................................................................................................... 140
GUILLAUMON, PEDRO VINICIUS....................................................................................................................................... 157
HÁ, KYU CHUL....................................................................................................................................................................... 191
HASHIMOTO, K......................................................................................................................................................................... 66
HASSAN, ISLAM..................................................................................................................................................................... 319
HATSUKAWA, YUICHI............................................................................................................................................................. 66
HAZIN, CLOVIS A.....................................................................................................................................86; 278; 279; 280; 285
HERNÁNDEZ, NELIS BLANCO.............................................................................................................................................. 89
HERNÁNDEZ-VALDÉS, DANIEL.......................................................................................................................................... 206
HERRERA, CIRO MÁRQUEZ................................................................................................................................................ 241
HIDALGO, PABLO ANTONIO MENDOZA............................................................................................................................. 93
HILDEBRAND HEIKE............................................................................................................................................................ 227
HONORATO, ELIANE VALENTIM................................................................................................................................ 233; 279
HORSKY, JIRI........................................................................................................................................................................... 283
HORVAT, MILENA..................................................................................................................................................................... 38
HRUBÝ, MARTIN...................................................................................................................................................... 51; 110; 305
HUET, SARAH DAMASCENO PINHEIRO.................................................................................................................... 217; 218
HUTCHEON, IAN D................................................................................................................................................................... 57
İÇHEDEF, ÇIĞDEM............................................................................................................................................................62; 111
IOANNIDOU, ALEXANDRA.................................................................................................................................................. 315
IWAHARA, AKIRA............................................................................................................................................................ 50; 148
JAĆIMOVIĆ, RADOJKO............................................................................................................................................... 38; 71; 92
JAÚREGUI-HAZA, ULISES.................................................................................................................................................... 206
JENDELOVÁ, PAVLA.............................................................................................................................................................. 305
JEONG, JONG TAE.................................................................................................................................................................. 197
JESUS, EDGAR FRANCISCO OLIVEIRA DE............................................................................................................... 258; 261
JIPA, SILVIU............................................................................................................................................................................. 188
JUCHNESKI, NICHELE CRISTINA DE FREITAS................................................................................................................ 296
JULIEN-DAVID, DIANE.......................................................................................................................................................... 220
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JUNG, YOONHEE.................................................................................................................................................................... 276
KADŁUBOWSKI, SŁAWOMIR...............................................................................................................................................115
KALMYKOV, STEPAN N.................................................................................................................................................... 65; 67
KAMENIK, JAN................................................................................................................................................................. 56; 297
KANG, MUN JÁ....................................................................................................................................................................... 276
KARANOVIĆ, GORANA......................................................................................................................................................... 182
KATO, LILIAN SEIKO..................................................................................................................................................... 256; 257
KAVASI, NORBERT................................................................................................................................................................. 104
KAWASSAKI, RODRIGO K.................................................................................................................................................... 176
KCIUK, GABRIEL...................................................................................................................................................................... 78
KILÇAR, AYFER YURT................................................................................................................................................... 112; 208
KILDIR, MEHMET..................................................................................................................................................................... 98
KIM, HYUNCHEOL................................................................................................................................................................. 276
KIM, KWANG-WOOK..............................................................................................................................................................117
KIM, KYUNGSU S................................................................................................................................................................... 197
KIYAN, LUDMILA DE YSASA POZZO................................................................................................................................. 181
KOIKE, AMANDA CRISTINA RAMOS......................................................................................................................... 185; 186
KOSTER-AMMERLAAN, ANNEKE...................................................................................................................................... 239
KRACHLER, MICHAEL............................................................................................................................................................ 90
KRAUSOVÁ, IVANA............................................................................................................................................................... 273
KRIST, PAVEL.......................................................................................................................................................................... 273
KUČERA, JAN.................................................................................................................................................................... 56; 283
KUČKA, JAN.............................................................................................................................................................. 51; 110; 305
KULENKAMPFF, JOHANNES................................................................................................................................................ 227
KULYAKO, Y. M....................................................................................................................................................................... 134
KULYUKHIN, SERGEY A............................................................................................................................... 127; 128; 129; 131
KUNTZ, FLORENT.................................................................................................................................................................. 220
LANGE, CAMILA NEVES....................................................................................................................................................... 142
LAPSHINA, ELENA V.......................................................................................................................................................... 65; 67
LARANJEIRA, ADILSON DA SILVA............................................................................................................................... 50; 306
LATINI, ROSE M........................................................................................................................................................................ 85
LAVANDERA, RAFAEL ALVAREZ SARANDES.................................................................................................................... 90
LEAL, ALEXANDRE SOARES............................................................................................................................................... 158
LEÃO, RENATA LINS CARNEIRO........................................................................................................................................ 215
LEE, EIL-HEE............................................................................................................................................................................117
LEE, JI YOUNG........................................................................................................................................................................ 197
LEE, KEUN-YOUNG................................................................................................................................................................117
LEE, KIL YONG....................................................................................................................................................................... 191
LEE, SEUNG YEOP.................................................................................................................................................................. 197
LEITAO, ROBERTA GAMA.................................................................................................................................................... 240
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
LEIVAS, TOMAZ PUGA.......................................................................................................................................................... 237
LEJBMAN, IUDA D. GOLDMAN VEL.................................................................................................................................. 157
LEONARDO, LUCIO............................................................................................................................................................... 124
LIMA, CARLA FLÁVIA DE.................................................................................................................................................... 155
LIMA, CELSO VIEIRA DE...................................................................................................................................................... 230
LIMA, CLÁUBIA PEREIRA BEZERRA................................................................................................................................... 92
LIMA, FERNANDO ROBERTO DE ANDRADE................................................................................................................... 233
LIMA, NELSON BATISTA DE.......................................................................................................................................... 79; 137
LOBO, VALERIAN................................................................................................................................................................... 123
LOPES, RICARDO TADEU.........................................................................................................50; 84; 140; 148; 203; 240; 261
LORDEL, SONIA...................................................................................................................................................................... 220
LOUREIRO, JAMIR DOS SANTOS........................................................................................................................................ 148
LUGÃO, ADEMAR BENEVOLO ................................................................................................... 115; 181; 183; 187; 188; 210
LUNGULESCU, MARIUS EDUARD........................................................................................................................................ 80
LYCZKO, MONIKA................................................................................................................................................................... 78
MAÇÃS, BENVINDO.............................................................................................................................................................. 177
MACEDO, OCTAVIO............................................................................................................................................................... 284
MACHADO, EDIMAR C......................................................................................................................................................... 203
MACHADO, WILSON............................................................................................................................................................. 203
MADI FILHO, TUFIC............................................................................................................................................................... 157
MÁDLÍKOVÁ, MARCELA..................................................................................................................................................... 273
MÁDUAR, MARCELO FRANCIS.......................................................................................................................................... 301
MAFFEZZOLI, NICCOLÒ................................................................................................................................................. 58; 277
MAGALHÃES, MARCELO DA ROCHA LEÃO DE.............................................................................250; 251; 252; 253; 254
MAGGI, VALTER............................................................................................................................................................... 58; 277
MAHIQUES, MICHEL MICHAELOVITCH DE..................................................................................................................... 192
MAIHARA, VERA AKIKO......................................................................................................................149; 152; 162; 173; 231
MALMBECK, RIKARD............................................................................................................................................................. 90
MAMANI, NILO FRANCISCO CANO........................................................................................................................... 154; 320
MANENTI, SIMONE.......................................................................................................................................................... 61; 315
MANSOUR, A. ......................................................................................................................................................................... 288
MARCHIONI, ERIC................................................................................................................................................................. 220
MARIANO, NEIDE APARECIDA........................................................................................................................................... 229
MARINESCU, MARIANA MĂDĂLINA................................................................................................................................ 187
MARINESCU, VIRGIL............................................................................................................................................................... 80
MARTINELLI, JOSÉ ROBERTO............................................................................................................................................... 79
MARTÍNEZ, MARIA ISABEL VEGA..................................................................................................................................... 256
MATTOVA, JANA............................................................................................................................................................... 51; 110
MAZZILLI, BARBARA P...........................................................................................................................77; 216; 232; 272; 318
MAZZOCCHI, VERA LÚCIA.................................................................................................................................................. 137
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MCFARLAND, AARON........................................................................................................................................................... 209
MEDINE, EMIN ILKER........................................................................................................................................................... 208
MEDRADO HECTOR HUGO SILVA..................................................................................................................................... 296
MELO, ANA MARIA MENDONÇA DE ALBQUERQUE...................................................................................................... 253
MÉLO, JULYANNE TORRES BEZERRA DE......................................................................................................................... 253
MENDES, BRUNO MELO............................................................................................................................................... 308; 317
MENEZES, ELIENE G. R......................................................................................................................................................... 267
MENEZES, MARIA ÂNGELA DE BARROS CORREIA......................................................................................... 92; 156; 175
MESTNIK FILHO, JOSÉ.......................................................................................................................................................... 137
METAIRON, SABRINA............................................................................................................................................................. 55
MIELKE, S. L............................................................................................................................................................................ 228
MIKELIC, IVANKA LOVRENČIĆ.......................................................................................................................................... 193
MILAN, MARVIC ORTUETA.................................................................................................................................................... 89
MILANOVIĆ, IVANA.............................................................................................................................................................. 182
MIRANDA JUNIOR, PEDRO.................................................................................................................................................. 301
MIRANDA, MARCIA VALÉRIA DE FÁTIMA DA ENCARNAÇÃO SÁ............................................................................. 172
MITTANI, JUAN C. R.............................................................................................................................................................. 153
MIZERA, JIŘÍ........................................................................................................................................................... 271; 273; 297
MONTEL, ALINE MONEZI..................................................................................................................................................... 246
MOON, JEI-KWON...................................................................................................................................................................117
MORA, MARIA ISABEL GRACIA........................................................................................................................................... 49
MORAES, MARCO ANTÔNIO PROENÇA VIEIRA DE............................................................................................... 106; 195
MORALES, OMAR YAHIR............................................................................................................................................... 49; 294
MOREIRA, DENISE SIMÕES................................................................................................................................................... 50
MOREIRA, EDSON GONÇALVES................................................................................................................. 147; 149; 162; 259
MOREIRA, FLÁVIO HENRIQUE DE SOUZA............................................................................................................... 299; 300
MOREIRA, LUCIANA MARA COSTA................................................................................................................................... 204
MOURA, EDUARDO............................................................................................................................................................... 286
MÜFTÜLER, ZÜMRÜT FAZILET BIBER..................................................................................................................... 112; 208
MUNITA, CASIMIRO SEPULVEDA............................................................................................................... 153; 154; 244; 255
NAMIHAS, MARCO SAMULE UBILLUS............................................................................................................................... 93
NASCIMENTO, ALESXANDRO F.......................................................................................................................................... 253
NASCIMENTO, JOÃO EUDES DO................................................................................................................................ 215; 311
NASCIMENTO, LEONARDO TAFAS CONSTANTINO DO................................................................................................ 309
NASCIMENTO, NATALIA CASSIA DO ESPIRITO SANTO................................................................................ 215; 221; 321
NASCIUTTI, LUIZ E................................................................................................................................................................ 240
NEGRINI NETO, OSVALDO..................................................................................................................................................... 79
NETO, THAIS S. P.................................................................................................................................................................... 176
NEVES, ARTHUR O. P............................................................................................................................................................. 260
NEVES, EDUARDO GÓES...................................................................................................................................................... 154
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
NEVES, MARIA JOSÉ..................................................................................................................................................... 204; 205
NEVES, MAURÍCIO DAVID MARTINS DAS....................................................................................................................... 237
NIEVOLA, CATARINA C.......................................................................................................................................................... 91
NISTI, MARCELO BESSA................................................................................................................................................ 77; 216
NORMAN, ERIC B................................................................................................................................................................... 157
NOVÝ, ZBYNEK........................................................................................................................................................................ 51
OLIVEIRA JUNIOR, OLIVIO PEREIRA DE.......................................................................................................................... 100
OLIVEIRA, ALINE SABASTIANE GONÇALES RAMOS DE............................................................................................. 124
OLIVEIRA, ANTÔNIO EDUARDO DE.......................................................................................................................... 148; 306
OLIVEIRA, ARNO HEEREN DE............................................................................................................................................ 141
OLIVEIRA, DAVI FERREIRA DE........................................................................................................................................... 260
OLIVEIRA, ENEAS TAVARES DE......................................................................................................................................... 171
OLIVEIRA, LUÍS CLÁUDIO DE............................................................................................................................................ 274
OLIVEIRA, LUIS FERNANDO DE......................................................................................................................................... 260
OLIVEIRA, M. BEATRIZ P. P.................................................................................................................................................. 184
OLIVEIRA, MARA CRISTINA L. DE............................................................................................................................. 163; 164
OLIVEIRA, MÉRCIA LIANE DE............................................................................................................ 215; 221; 233; 311; 321
OLIVEIRA, SONIA MARIA BARROS DE..................................................................................................................... 160; 243
OREŠČANIN, VIŠNJA............................................................................................................................................................. 193
ORTEGA, GRACIELA ZARAZUA............................................................................................................................ 72; 241; 293
OSSO JUNIOR, JOÃO ALBERTO................................................................................................................................... 211; 310
OSTAPENKO, VALENTINA S............................................................................................................................................. 65; 67
PACHECO, ADRIANO M. G.................................................................................................................................................... 177
PADILLA-SORIANO, EDGAR................................................................................................................................................ 169
PAIVA, JOSÉ DANIEL SOARES DE............................................................................................................................... 252; 254
PALMIERI, HELENA EUGÊNIA LEONHARDT........................................................................................................... 146; 175
PALUMBO JR, ANTONIO....................................................................................................................................................... 240
PARENTE, CARLOS BENEDICTO RAMOS......................................................................................................................... 137
PARIZEK, MARTIN..................................................................................................................................................................110
PARK, MIN-SUNG....................................................................................................................................................................117
PARRA, DUCLERC FERNANDES......................................................................................................................................... 181
PASCHOLATI, PAULO R......................................................................................................................................................... 157
PATCHINEELAM, SAMBASIVA RAO..................................................................................................................................... 84
PECEQUILO, BRIGITTE ROXANA SOREANU................................................................................................................... 145
PEREIRA JUNIOR, SERGIO MATIAS................................................................................................................................... 162
PEREIRA, ELIANA.................................................................................................................................................................. 186
PEREIRA, SUELI YOSHINAGA............................................................................................................................................. 299
PEREIRA, WALSAN W............................................................................................................................................................ 284
PEREVALOV, S. A.................................................................................................................................................................... 134
PÉREZ, GUILLERMO MESA.................................................................................................................................................... 89
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4th-INCC 2014 I 4th International Nuclear Chemistry Congress
PÉREZ, MIGUEL ANGEL ZÚÑIGA.......................................................................................................................... 49; 196; 293
PÉREZ, PEDRO ÁVILA..................................................................................................................................................... 72; 241
PEREZ-REBOLLEDO, ANAYIVE........................................................................................................................................... 312
PERROTTA, JOSÉ AUGUSTO.................................................................................................................................................. 39
PESSINE, ELISABETE JORGE............................................................................................................................................... 237
PETRÍK, MILOS......................................................................................................................................................................... 51
PETRONI, ROBSON................................................................................................................................................................ 147
PIERETTI, EURICO FELIX..................................................................................................................................................... 237
PIJEIRA, MARTHA SAHYLÍ ORTEGA.................................................................................................................................. 138
PILLIS, MARINA FUSER................................................................................................................................................ 163; 164
PIMENTA, ADRIANO MONTEIRO DE CASTRO................................................................................................................. 312
PINELA, JOSÉ VIRGÍLIO SANTULHÃO.............................................................................................................................. 184
PINHEIRO, NUNO M. B.......................................................................................................................................................... 177
PIZARRO-LOU, LUIS.............................................................................................................................................................. 206
POBLANO-BATA, JOSEFINA................................................................................................................................................. 241
POGGI, CLAUDIA MIRIAM BRAGA............................................................................................................................ 278; 285
POLEDNA, ROBERTO.................................................................................................................................................... 143; 306
PORTELA, JORGE BORROTO............................................................................................................................................... 138
PORTO, BÁRBARA ABRANCHES DE ARAUJO.................................................................................................................. 204
POUČKOVÁ, PAVLA................................................................................................................................................. 51; 110; 305
PREVITALI, EZIO.............................................................................................................................................................. 58; 277
PYTELOVÁ, INGRID.............................................................................................................................................................. 283
QUEIROZ, RICARDO A.......................................................................................................................................................... 296
QUINTANA, BEGOÑA............................................................................................................................................................ 151
RAMOS, ERIKA COAGLIA TRINDADE............................................................................................................................... 229
ŘANDA, ZDENĚK................................................................................................................................................... 271; 273; 297
RAO, T. K. GUNDU.................................................................................................................................................................. 320
REDÍGOLO, MARCELO MIYADA........................................................................................................................................... 55
REIS, ROGÉRIO ALVES DE SOUSA...................................................................................................................................... 161
RENZI, LUIGINA..................................................................................................................................................................... 105
RÉVAY, ZSOLT........................................................................................................................................................................... 40
REYES, ANDRÉS ENRIQUE LAI........................................................................................................................................... 298
RIBEIRO JÚNIOR, IBERÊ SOUZA......................................................................................................................................... 249
RIBEIRO, ANDREZA PORTELLA.................................................................................................................................... 91; 192
RIBEIRO, FREDERICO HADDAD......................................................................................................................................... 204
RIBEIRO, ROBERTA DE OLIVEIRA RESENDE................................................................................................................... 258
RIBEIRO, RODHOLFO MACIEL DE MENDONÇA............................................................................................................. 258
RIBEIRO, ROGÉRIO BARIA.................................................................................................................................................. 154
ROCCA, RENÉ ROJAS............................................................................................................................................................ 316
ROCHA, ADRIANA MÁRCIA GUIMARÃES........................................................................................................................ 308
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4th International Nuclear Chemistry Congress I 4th-INCC 2014
ROCHA, FLÁVIO R......................................................................................................................................................... 160; 199
ROCHA, RIQUE JONES FERREIRA XAVIER DA................................................................................................................ 198
ROCHA, ROSIANA ROCHO................................................................................................................................................... 150
RODRIGUES, DEMERVAL LEONIDAS.................................................................................................................................. 79
RODRIGUES, FLÁVIO THIHARA......................................................................................................................................... 220
RODRIGUES, RAFAELA E. A. V.............................................................................................................................................. 86
RODRIGUES, VANESSA S...................................................................................................................................................... 245
RODRÍGUEZ-RIERA, ZALUA................................................................................................................................................ 206
ROSA, DANNIELE SCARPIN................................................................................................................................................... 79
ROSA, MYCHELLE MUNYCK LINHARES................................................................................................................. 229; 231
ROSADA, ALBERTO............................................................................................................................................................... 105
ROSIAK, JANUSZ M................................................................................................................................................................115
ROSSI, EDUARDO HAROLDO MONTOYA........................................................................................................................... 93
SABADINI-SANTOS, ELISAMARA...................................................................................................................................... 203
SAHOO, SARATA K................................................................................................................................................................. 104
SAID, DAPHNE DE SOUZA................................................................................................................................................... 310
SAIKI, MITIKO....................................................................................................... 144; 150; 158; 163; 164; 173; 174; 176; 249
SALA, ELENA............................................................................................................................................................................ 58
SALAS, PATRICIA SOCORRO BEDREGAL........................................................................................................................... 93
SALLES, PAULA MARIA BORGES DE................................................................................................................................. 156
SALVADOR, VERA LÚCIA RIBEIRO............................................................................................................................ 161; 162
SANCHES, FRANCIS ANNA CARDOSO REIS DE ALMEIDA........................................................................................... 260
SANCHEZ, ELADIO F............................................................................................................................................................. 312
SANTOS JÚNIOR, JOSÉ ARAÚJO DOS.......................................................................................................................... 89; 194
SANTOS, ANDERSON R. L.................................................................................................................................................... 284
SANTOS, CARLOS A. N.......................................................................................................................................................... 240
SANTOS, DANIEL M............................................................................................................................................................... 312
SANTOS, ELAINE VASCONCELOS DOS..............................................................................................................................311
SANTOS, ELIANE CONCEIÇÃO DOS.......................................................................................................................... 174; 176
SANTOS, JOSÉ OSMAN DOS........................................................................................................................................ 244; 255
SANTOS, LUÍS GUSTAVO COFANI DOS............................................................................................................. 262; 263; 264
SANTOS, MAURÍCIO CÉSAR FERREIRA ........................................................................................................................... 289
SANTOS, MAURO JOSÉ DOS................................................................................................................................................ 255
SANTOS, OLAIR DOS............................................................................................................................................................. 171
SANTOS, RAMON SILVA DOS.............................................................................................................................................. 260
SANTOS, RAQUEL GOUVEA DOS............................................................................................................... 205; 309; 312; 246
SANTOS, SANDRA MARIA CHEBERLE DOS............................................................................................................. 229; 231
SANTOS, SANTIAGO SCARCELLI....................................................................................................................................... 301
SANTOS, SIMONE SILVEIRA NERY DA SILVA COFANI DOS.................................................................................. 262; 263
SANTOS, UANDA PAULA DE MEDEIROS DOS................................................................................................................. 152
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4th-INCC 2014 I 4th International Nuclear Chemistry Congress
SANTOS, WAGNER GOUVÊA DOS...................................................................................................................................... 246
SANTOS-BUELGA, CELESTINO........................................................................................................................................... 185
SARKIS, JORGE EDUARDO DE SOUZA................................................................................................................................ 79
SARRIÉS, GABRIEL ADRIÁN................................................................................................................257; 262; 263; 264; 298
SATO, IVONE MULAKO........................................................................................................................................... 55; 161; 162
SATO, N....................................................................................................................................................................................... 66
SATO, T....................................................................................................................................................................................... 66
SAUEIA, CÁTIA HELOISA ROSIGNOLI................................................................................................................ 77; 216; 272
SCAGLIUSI, SANDRA REGINA.................................................................................................................................... 187; 188
SCAPIN, MARCOS A............................................................................................................................................................... 243
SCHIAVINATO ISABEL CRISTINA AZEVEDO.................................................................................................................. 256
SCHYMURA, STEFAN............................................................................................................................................................ 227
SECCO, MARCELLO............................................................................................................................................................... 238
SEDLACEK, ONDREJ..............................................................................................................................................................110
SEMMLER, MARILIA GABRIELA MIRANDA CATHARINO............................................................................................ 272
SEO, EMÍLIA SATOSHI MIYAMARU............................................................................................................................ 137; 267
SEPE, FERNANDA PEIXOTO................................................................................................................................................. 158
SHADRIN, ANDREY YU......................................................................................................................................... 129; 131; 134
SHI, YOUQING......................................................................................................................................................................... 170
SILVA FILHO, CRESCÊNCIO ANDRADE..................................................................................................................... 278; 285
SILVA JUNIOR, OSWALDO PEREIRA VILELA DA............................................................................................................. 164
SILVA NETO, PAULO CORREIA DA............................................................................................................................. 247; 248
SILVA, ADONIS MARCELO SALIBA.................................................................................................................................... 171
SILVA, ARYKERNE NASCIMENTO CASADO DA.............................................................................................................. 194
SILVA, BÁRBARA CORRIGLIANO DA.................................................................................................................................. 91
SILVA, CARLOS JOSÉ DA........................................................................................................................................ 50; 148; 306
SILVA, CAROLINA FERNANDA DA..................................................................................................................................... 198
SILVA, FELIPE HENRIQUE DE SOUZA................................................................................................................................ 312
SILVA, FELLIPE SOUZA DA.................................................................................................................................................. 284
SILVA, HUGO LEONARDO LEMOS..................................................................................................................................... 219
SILVA, IEDA DE SOUZA......................................................................................................................................................... 274
SILVA, JOSÉ WANDERLEY S. DA......................................................................................................................................... 140
SILVA, JULIANA BATISTA DA...................................................................................................................................... 308; 309
SILVA, LEONARDO GONDIM DE ANDRADE E................................................................................................................. 289
SILVA, NIVALDO CARLOS DA...................................................................................................................................... 299; 300
SILVA, PAULO S. CARDOSO DA...........................................................................................160; 165; 173; 199; 232; 243; 295
SILVA, RAQUEL MEDEIROS DA........................................................................................................................................... 106
SILVA, RONALDO LINS DA................................................................................................................................................... 143
SILVA, SHARLLENY ALVES.................................................................................................................................................. 242
SILVA, WALDECY A.................................................................................................................................................................. 86
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SILVA, WANILSON LUIZ........................................................................................................................................................ 242
SILVEIRA, MARINA BICALHO..................................................................................................................................... 308; 309
SILVEIRA, PATRÍCIA B................................................................................................................................................... 278; 285
SILVEIRA-LACERDA, ELISÂNGELA DE PAULA............................................................................................................... 246
SKÁLA, ROMAN..................................................................................................................................................................... 297
ŠKARO, KRUNOSLAV............................................................................................................................................................ 193
SKODOVA, MICHAELA............................................................................................................................................................ 51
SLUIJS, ROBBERT VAN............................................................................................................................................................ 71
SMODIŠ, BORUT....................................................................................................................................................................... 83
SOARES, EMÍLIO ALBERTO AMARAL............................................................................................................................... 244
SONDERMANN, MELISSA NOGUEIRA......................................................................................................................... 84; 203
SORDO FILHO, GIOVANNI DEL........................................................................................................................................... 243
SOUČEK, PAVEL........................................................................................................................................................................ 90
SOUSA, EDUINETTY CECI PEREIRA MOREIRA DE......................................................................................................... 272
SOUSA, EVELY ELEN............................................................................................................................................. 248; 252; 254
SOUSA, TALITA....................................................................................................................................................................... 274
SOUZA, JÔNAS HENRIQUE ALVES DE............................................................................................................................... 247
SOUZA, MARIA INÊS S............................................................................................................................................................ 85
SOUZA, PEDRO A. V. R.......................................................................................................................................................... 240
SOUZA, VIVIANNE LÚCIA BORMANN DE.......................................................................................................................... 86
STEPÁNEK, PETR..................................................................................................................................................................... 51
STIBILJ, VEKOSLAVA.............................................................................................................................................................. 38
STOPIC, ATTILA........................................................................................................................................................................ 71
STUDENOVSKY, MARTIN......................................................................................................................................................110
SULIEMAN, ABDELMONEIM............................................................................................................................................... 319
SUSSA, FÁBIO VITÓRIO........................................................................................................................................................ 232
SUZUKI, KATIA NORIKO................................................................................................................................................. 84; 203
SVITÁKOVÁ, ROMANA......................................................................................................................................................... 283
TÁBORSKÝ, JAN..................................................................................................................................................................... 273
TADDEI, MARIA HELENA TIROLLO............................................................................................................. 41; 229; 231; 300
TALHAVINE, MARCIO............................................................................................................................................................. 79
TAPPIZ, BRUNO...................................................................................................................................................................... 199
TATUMI, SONIA HATSUE................................................................................................................................ 97; 153; 154; 316
TAUHATA, LUIZ................................................................................................................................................................ 50; 148
TEJEDA, YUNIEL.................................................................................................................................................................... 138
TEJERO, JUAN MANUEL NAVARRETE.................................................................................................49; 169; 196; 293; 294
TEKSÖZ, SERAP.................................................................................................................................................................62; 111
TELLO, CLÉDOLA CÁSSIA OLIVEIRA DE......................................................................................................................... 275
THOMAS, KEENAN J.............................................................................................................................................................. 157
THOMPSON, LARISSA........................................................................................................................................................... 219
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THRUHLAR, D. G.................................................................................................................................................................... 228
TICIANELLI, REGINA BECK......................................................................................................................................... 144; 238
TOPAL, GÖKÇEN.................................................................................................................................................................... 207
TORRECILHA, JEFFERSON KOYAISHI............................................................................................................................... 295
TORRES, DÉBORA HERNÁNDEZ........................................................................................................................................... 89
TOYOSHIMA, A. ....................................................................................................................................................................... 66
TRAMONTE, KEILA MODESTO........................................................................................................................................... 192
TRINDADE, BRUNO MACHADO......................................................................................................................................... 317
TROJANOWICZ, MAREK......................................................................................................................................................... 78
TSUKADA, K............................................................................................................................................................................. 66
TUDELA, DIEGO RENAN GIGLIOTI.................................................................................................................................... 153
UÇAR, ESER........................................................................................................................................................................62; 111
ULANSKI, PIOTR.....................................................................................................................................................................115
ÜNAK, PERIHAN................................................................................................................................................. 52; 62; 112; 208
ÜNAK, TURAN.......................................................................................................................................................................... 42
URBÁNEK, PETR...................................................................................................................................................................... 51
USTINOV, OLEG A.......................................................................................................................................................... 129; 131
UZARAS, CANSU.................................................................................................................................................................... 208
VARCA, GUSTAVO HENRIQUE COSTA................................................................................................................................115
VASCONCELLOS, MARINA BEATRIZ AGOSTINI..................................................................................................... 149; 259
VASILIEV, ALEKSANDR N................................................................................................................................................ 65; 67
VEJA, SAMUEL TEJEDA.................................................................................................................................. 72; 196; 241; 293
VETRÍK, MIROSLAV................................................................................................................................................................. 51
VIANA, ALINE GONZALEZ................................................................................................................................................... 140
VIEIRA, JOSÉ WILSON.......................................................................................................................................................... 194
VIEIRA, VANESSA MOTA...................................................................................................................................................... 275
VILELA, ÊUDICE CORREIA.......................................................................................................................................... 221; 321
VILLAVICENCIO, ANNA LUCIA CASAÑAS HAASIS................................................................................................ 185; 220
VIVOLO, VITOR.............................................................................................................................................................. 217; 218
VOSKRESENSKAYA, YULIA A..................................................................................................................................... 129; 131
VREČA, POLONA...................................................................................................................................................................... 38
VRECHI, TALITA APARECIDA DE MORAES...................................................................................................................... 210
WATANABE, SHIGUEO.................................................................................................................................................. 154; 320
WIIKMANN, LUIZA OIDE...................................................................................................................................................... 264
WILLIAMS, ROSS W................................................................................................................................................................. 57
WINCKEL, STEFAAN VAN...................................................................................................................................................... 90
WOLSZCZAK, MARIAN..........................................................................................................................................................115
WOLTERBEEK, HUBERT T.................................................................................................................................................... 177
YOKOYAMA, LEONARDO Q................................................................................................................................................ 258
YOON, YOON YEOL............................................................................................................................................................... 191
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YOSHIDA, SATOSHI............................................................................................................................................................... 104
YUSOV, A. B. ........................................................................................................................................................................... 133
ZADINOVA, MARIE.................................................................................................................................................................110
ZAHARESCU, TRAIAN.................................................................................................................................... 80; 181; 187; 188
ZAHN, GUILHERME SOARES.............................................................................................................................. 144; 238; 249
ŽÁK, KAREL............................................................................................................................................................................ 297
ZAMBONI, CIBELE BUGNO.................................................................................................................................................... 55
ZEISLER, ROLF......................................................................................................................................................................... 44
ZEN, HELOÍSA AUGUSTO............................................................................................................................................. 187; 188
ZHUIKOV, BORIS L............................................................................................................................................................. 65; 67
ZINI, JOSIANE......................................................................................................................................................................... 310
344
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2014
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