Centro de Desenvolvimento da Tecnologia Nuclear - CDTN
Comissão Nacional de Energia Nuclear - CNEN
Amir Zacarias Mesquita, ScD
http://buscatextual.cnpq.br/buscatextual/visualizacv.do?metodo=apresentar&id=
K4760633D4&idiomaExibicao=2
[email protected]
[email protected]
[email protected]
Bibliographic Citation: MESQUITA, A.Z.; Mesquita, Amir Z
Amir Zacarias Mesquita is Doctor of Science in Chemical Engineering - State University of
Campinas/Brazil (2005), Master of Science and Nuclear Technologies - Federal University of Minas
Gerais/Brazil (1981) and graduated in Electrical Engineering - Federal University of Minas
Gerais/Brazil (1978). He is Titular Researcher at Nuclear Technology Development Center (CDTN), a
research institute of the Brazilian Nuclear Energy Commission (CNEN), and Scholarship of
Productivity and Technological Development of Innovative Extension at Brazilian Council for
Scientific and Technological Development (CNPq). Professor and Collegiate Board Member of the
Postgraduate Program in Science, Radiation Technology, Minerals and Materials at CDTN. Dr.
Mesquita is involved in research in nuclear engineering with an emphasis on reactor technology,
working mainly on thermo-fluid dynamics and reactor physics. He performs experimental studies on
thermal-hydraulic and neutronic of research reactor on topics such as heat transfer, temperature,
mass flow, nuclear fuel, power, neutrons flux, reactivity, instrumentation for control of nuclear
reactor operational parameters, and data acquisition systems. He is author of more than one
hundred technical papers published in international journals and conference proceedings. His
research focuses mainly in studies and experiments on alternatives for monitoring the energy
released by nuclear fissions, in order to improve reliability and safety of reactors operation.
Nominated twice by the "Eni Scientific Secretariat" for The Eni Award (2011 and 2012, Azienda
Generale Italiana Petroli - AGIP), class: Protection of the Environment Prize. Dr. Mesquita is
Coordinator of the Brazilian Project: Theoretical and Experimental Research on Thermal-Hydraulic
and Neutronic in Nuclear Research Reactors funded by CDTN/CNEN, the Research Support
Foundation of the State of Minas Gerais (FAPEMIG) and Brazilian Council for Scientific and
Technological Development (CNPq). He has been collaborating for projects with other research
foundations, such as the Federal University of Minas Gerais (UFMG), State University of Campinas
(UNICAMP), Coordination for the Improvement of Higher Education Personnel (CAPES), and
Research and Projects Financing (FINEP). He is consultant for Iberian-American Development
Program for Science and Technology (CYTED) and the Education Board of Brazilian Nuclear Energy
Commission (CNEN). He is expert of the International Atomic Energy Agency (IAEA)
(Colombia/Marocco), and the National Centre of Science and Technology Evaluation (Ministry of
Education and Science of Kazakhstan). He is member of the Brazilian Association for Nuclear
Engineering (ABEN), and Brazilian Society of Mechanical Sciences and Engineering (ABCM). He is
professor of training course for Brazilian nuclear reactors operators, and Senior Operator. He is
reviewer of several international conferences and journals such as Annals of Nuclear Energy and
Journal of ASTM International. Book author: Digital Control System Simulation for Nuclear Reactor
Neutronic Parameters - Nova Science Publishers Inc. NY (2012). Book editor: Current Research in
Nuclear Reactor Technology in Brazil and Worldwide (2013), and Nuclear Reactors (2012) - InTech
Publisher (Croatia). Editorial Board Member of several journals such as: Energy and Environment
Research (Canadian Center of Science and Education), International Journal of Energy Engineering
(USA), International Journal of Advanced Renewable Energy Research, Thermal Energy and Power
Engineering, and Journal on Nuclear Energy Management and Safety (UK).
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Centro de Desenvolvimento da Tecnologia Nuclear - CDTN
Comissão Nacional de Energia Nuclear - CNEN
Bibliographical Production
Books:
1)
Mesquita, A.Z. Current Research in Nuclear Reactor Technology in Brazil and Worldwide. (Editor). 1. ed.
Rijeka/Croatia: InTech - Open Access Publisher, v. 1. 336p. ISBN: 9809533078507. DOI: 10.5772/56032. Feb.
2013.
2)
Mesquita, A.Z. Nuclear Reactors (Editor). 1. ed. Rijeka/Croatia: InTech - Open Access Publisher, v. 1. 338p.
ISBN: 9789535100188. . DOI: 10.5772/1919. Feb. 2012.
Mesquita, A.Z.; Pinto, A.J.; Tello, C.C.O.; Lameiras, F.S. Digital Control System Simulation for Nuclear Reactor
Neutronic Parameters. 1. ed. Hauppauge, NY/USA: Nova Science Publishers Inc., v.1, 35p. ISBN:
9781619421325. 2012.
3)
Book Chapters:
1)
Rezende, H.C.; Santos, A.A.C.; Navarro, M.A.; Mesquita, A.Z. Chapter 1 - Experimental Investigation and
Computational Validation of Thermal Stratification in Piping Systems of PWR Reactors. In: Amir Z. Mesquita
(Editor), Ms Mirna Cvijic. (Org.). Current Research in Nuclear Reactor Technology in Brazil and Worldwide. 1 ed.
Rijeka: InTech - Open Access Publisher, v. 1, p. 3-27. ISBN: 9809533078507. DOI: 10.5772/52614. 2013.
2)
Palma, D.A.P.; Gonçalves, A.C.; Martinez A.S; Mesquita, A.Z. Chapter 2 - New Methods in the Doppler
Broadening Function Calculation. In: Amir Z. Mesquita (Editor); Ms Mirna Cvijic. (Org.). Current Research in
Nuclear Reactor Technology in Brazil and Worldwide. 1 ed. Rijeka: InTech - Open Access Publisher, v. 1, p. 2953. ISBN: 9809533078507. DOI: 10.5772/52464. 2013.
3)
Rodrigues, R.R.; Mesquita, A.Z. Design of a System for Fuel Elements Cladding Inspection of a Nuclear Research
Reactor. In: J.F. Silva Gomes and Shaker A. Meguid. (Org.). Recent Advances in Integrity-Reliability-Failure.
1ed.Porto: INEGI-Instituto de Engenharia Mecânica e Gestão Industrial, v. 1, p. 69-70. ISBN:
97897288262772013.
4)
Mesquita, A.Z.; Palma, D.A.P. Diversification of Processes to Measure Thermal Power of Nuclear Reactors. In:
Editor: A. Mendez-Vilas. (Org.). Book: Fuelling the Future: Advances in Science and Technologies for Energy
Generation, Transmission and Storage. 1ed.Florida: BrownWalker Press, v. 1, p. 419-423. ISBN:
9781612335582. 2012.
5)
Mesquita, A.Z.; Palma, D.A.P.; Costa, A.L.; Pereira, C.; Veloso, M.A.F.; Reis, P.A.L. Chapter 1: Experimental
Investigation of Thermal Hydraulics in the IPR-R1 TRIGA Nuclear Reactor. Editor: Amir Z. Mesquita & Petra
Zobic. Book: Nuclear Reactors. 1 ed. InTech - Open Access Publisher: Rijeka, Croatia, v. 1, p. 23-58. ISBN:
9789533084. DOI: 10.5772/25869. 2012.
6)
Mesquita, A.Z. Pinto, A.J. Tello, C.C.O. Chapter 4: Digital Control System Simulation for Nuclear Reactor
Neutronic Parameters. Book: Advances in Energy Research. Editor: Morena J. Acosta. Vol. 10. Ed. Nova Science
Publishers, Inc. NY, ISBN: 9781621008385. 2012.
7)
Mesquita, A.Z.; Costa, A.L.; Pereira, C.; Veloso, M.A.; Reis, P.A.L. Chapter 10 - Experimental Investigation of the
Onset of Subcooled Nucleate Boiling in an Open-Pool Nuclear Research Reactor. In: Prabhu, K.N.; Kobasko, N..
(Org.). Book: Film and Nucleate Boiling Processes. 1ed.West Conshohocken: ASTM International, , v. 1, p. 183197. ISBN: 9780803175204. 2012.
8)
Costa, L.C.; Pereira, C.; Silva, C.A.M.; Reis, P.A.L.; Veloso, M.A.F.; Soares, H. V.; Mesquita, A.Z.. Chapter 2: Safety
Studies and General Simulations of Research Reactors Using Nuclear Codes. Book: Nuclear Power - System
Simulations and Operation. Editor: Dr. Pavel Tsvetkov & Petra Zobic. Rijeka, Croatia: InTech - Open Access
Publisher, 1 ed., v. 2, p. 27-53. ISBN: 9789533075. DOI: 10.5772/17411. 2011.
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Centro de Desenvolvimento da Tecnologia Nuclear - CDTN
Comissão Nacional de Energia Nuclear - CNEN
Articles in Scientific Journals:
1.
Mesquita, A.Z.; Santos, A.A.C.; Rezende, H.C ; Palma, D.A.P. Performance of some operating parameters of a
TRIGA research reactor in natural convective cooling. International Journal of Nuclear Energy, Science and
Technology (Print), v. 8, p. 61-71, DOI: 10.1504/IJNEST.2014.057904. 2014.
2.
Santos, A.A.C.; Mesquita, A.Z.; Costa, F.C. ; Meireles, S.P.; Rezende, H.C. Flow Analysis in the Core of Pebble
Bed High Temperature Gas-Cooled Reactor. Journal of Applied Chemistry, v. 2, p. 116-134. ISSN/ISBN:
23480408. 2014.
3.
Mesquita, A.Z.; Rodrigues, R.R. Detection of the Departure from Nucleate Boiling in Nuclear Fuel Rod
Simulators. International Journal of Nuclear Energy, v. 2013, p. 1-7, doi.org/10.1155/2013/950129. 2013.
4.
Reis, P.A.L.; Costa, A.L.; Pereira, C.; Veloso, M. A. F.; Soares, H. V.; Mesquita, A.Z. Analysis of an Extreme Loss
of Coolant in the IPR-R1 TRIGA Reactor using a RELAP5 Model. Engenharia Térmica, v. 12, p. 46-50, 2013.
Santos, A.A.C.; Costa, F.C.; Mesquita, A.Z.; Rezende, H.C. Numerical Investigation of Flow in Generation IV
Pebble Bed Gas Cooled Core Reactors. International Journal of Energy and Power Engineering, v. 2, p. 69-76,
ISSN: 2326-957X (Print) ISSN: 2326-960X (Online) DOI: 10.11648/j.ijepe.20130202.16. 2013.
Mesquita, A.Z.; Palma, D.A.P. Detection of the Critical Heat Flux in Nuclear Fuel Rod Simulator. Studies in
Chemical Process Technology (SCPT), v. 1, p. 1-7, ISSN: 2328-2347 (Print). 2013.
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Mesquita, A.Z.; Santos, A.A.C.; Campolina, D.A.M.; Schweizer, F.L.A; Palma, D.A.P. Real-Time Monitoring of
Dynamic Behavior in the CDTN TRIGA Research Reactor. International Journal of Advanced Engineering
Applications, v. 1, p. 15-24,; Série: 5; ISSN/ISBN: 22777345. 2013.
8.
Mesquita, A.Z.; Santos, A.A.C.; Rezende, H.C.; Palma, D.A.P. Performance of some operating parameters of a
TRIGA research reactor in natural convective cooling. International Journal of Nuclear Energy, Science and
Technology (Print); ISSN/ISBN: 17416361. 2013.
9.
Reis, Patrícia A.L.; Costa, Antonella L.; Pereira, Claubia; Silva, Clarysson A.M.; Veloso, Maria A. F.; Mesquita,
Amir .Z. Sensitivity analysis to a RELAP5 nodalization developed for a typical TRIGA research reactor. Nuclear
Engineering and Design (Print), v. 242, p. 300-306, DOI:10.1016/j.nucengdes.2011.10.022. 2012.
10.
Mesquita, A.Z.; Costa, A.C.L.; Souza, R.M.G.P.; Palma, D.A.P. Medidas Experimentais de Parâmetros
Termohidráulicos no Núcleo de Reator Nuclear de Pesquisa. Revista Iberoamericana de Ingeniería Mecánica,
v. 16, p. 10-23, ISSN: 1137-2729. 2012.
Palma, D.A.P; Mesquita, A.Z.; Souza, R.M.G.P.; Martinez A.S. Real-Time Monitoring of Power and Neutron
Capture Cross Section in Nuclear Research Reactor. IAEA Publications - Research Reactors: Safe
Management and Effective Utilization, v. 1, p. 27-33; Série: IAEA-CN-18; ISSN/ISBN: 19912374. 2012.
Souza, R.M.G.P.; Mesquita, A.Z. Neutronic Tests in IPR-R1 TRIGA Reactor. IAEA Publications - International
Conference on Research Reactors: Safe Management and Effective Utilization, v. 1, p. 45-51, 2012; Série:
IAEA-188; ISSN/ISBN: 19912374. 2012.
Martínez, M.; Miró, R.; Verdú, G.; Pereira, C.; Mesquita, A.Z.; Chiva, S. Assessment of a computational fluid
dynamic (CFD) model for the IPR-R1 TRIGA research reactor. Transactions of the American Nuclear Society,
v. 106, p. 1006-1009. 2012.
Mesquita, A.Z.; Costa, A.C.L.; Souza, R.M.G.P. Modernisation of the CDTN IPR-R1 TRIGA Reactor
Instrumentation and Control. International Journal of Nuclear Energy, Science and Technology, v. 6, p. 153165. Editor: Alexander M. Agapov. ISSN: 1741-6361. DOI: 10.1504/IJNEST.2011.041649. July 2011.
Mesquita, A.Z.; Costa, A.L.; Pereira, C.; Veloso, M.A.F.; Reis, P.A.L. Experimental Investigation of the Onset of
Subcooled Nucleate Boiling in an Open-Pool Nuclear Research Reactor. Journal of ASTM International, v. 8,
p. 51-60. Editor: Sheldon W. Dean, Jr. Portland. ISSN: 1546-962X. DOI: 10.1520/JAI103193. July 2011.
Mesquita, A.Z.; Rezende, H.C.; Souza, R.M.G.P. Thermal Power Calibrations of the IPR-R1 TRIGA Reactor by
the Calorimetric and the Heat Balance Methods. Progress in Nuclear Energy, v. 53, p. 1-11. Editors: T.D.
Beynon & D.J. Dudziak. INSS: 0149-1970. DOI: 10.1016/j.pnucene.2011.08.003. Aug 2011.
Souza, R.M.G.P.; Mesquita, A.Z. Measurements of the Isothermal, Power and Temperature Reactivity
Coefficients of the IPR-R1 TRIGA Reactor. Progress in Nuclear Energy, v. 53, p. 257-306. Editors: T.D. Beynon
& D.J. Dudziak. ISSN: 0149-1970. DOI: 10.1016/j.pnucene.2011.06.010. August 2011.
Souza, R.M.G.P.; Mesquita, A.Z. Reactivity Balance in the IPR-R1 TRIGA Reactor. Progress in Nuclear Energy,
v. 53, p. 307-405. Editors: T.D. Beynon & D.J. Dudziak. ISSN: 0149-1970. DOI:
10.1016/j.pnucene.2011.06.011. August 2011.
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Comissão Nacional de Energia Nuclear - CNEN
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Mesquita, A.Z.; Rezende, H.C.; Ferreira, A.V. Monitoramento de parâmetros termohidráulicos do núcleo do
reator de pesquisa TRIGA IPR-R1. Revista Tecnologia (UNIFOR), v. 32, p. 145-153, Série: 2; ISSN/ISBN:
01018191. 2011;
Rezende, H.C.; Navarro, M.A.; Mesquita, A.Z.; Santos, A.A.C.; Jordão, E. Experiments on One-Phase
Thermally Stratified Flows in Nuclear Reactor Pipe Lines. Revista Científica ESIME Redalyc, v. 15, p. 17-24,
Instituto Politécnico Nacional México. Editor: Guillermo U. Calderón. ISSN 1665-0654. March,_2011.
Mesquita, A.Z.; Rezende, H.C. Monitoring of Coolant Flow Rate and Velocity in the Hot Channel of the IPR-R1
TRIGA Nuclear Reactor Core. Científica ESIME Redalyc- Instituto Politécnico Nacional México, v. 14, p. 55-60.
Editor: Guillermo Urriolagoitia Calderón. ISSN 1665-0654. June 2010.
Pinto, A.J.; Mesquita, A.Z.; Tello, C.C.O. Simulação da Evolução da Potência de Reatores Nucleares de
Pesquisa Utilizando o Software LabVIEW®. Revista Iberoamericana de Ingeniería Mecánica, v. 14, No. 1, p.
51-62, ISSN: 1137-2729. Editor: Francisco Alba Juez. San Juan, Argentina. April 2010.
23.
Mesquita, A.Z.; Pinto, A.J.; Cândido, M.A. Recuperação dos Termopares do Elemento Combustível
Instrumentado do Reator Nuclear TRIGA IPR-1. Revista Iberoamericana de Ingeniería Mecánica, v. 14, N o. 1,
p. 41-50, Editor: Francisco Alba Juez. San Juan, Argentina. April 2010.
24.
Mesquita, A.Z.; Rezende, H.C.; Souza, R.M.G.P. Comparação Entre o Método Calorimétrico e o Método do
Balanço Térmico na Calibração de Potência do Reator Nuclear de Pesquisa TRIGA IPR-R1. Revista
Iberoamericana de Ingeniería Mecánica, v. 14, No. 2, p. 03-12, Editor: Francisco Alba Juez. San Juan,
Argentina. ISSN: 1137-2729. October 2010.
25.
Mesquita, A.Z.; Rezende, H.C. Thermal Methods for On-Line Power Monitoring of the IPR-R1 TRIGA Reactor.
Progress in Nuclear Energy (New series), v. 52, p. 268-272. Elsevier Ltd. Editor T.D. Beynon, Oxford UK. ISSN:
0149-1970. doi:10.1016/j.pnucene.2009.07.013. April 2010.
26.
Mesquita, A.Z.; Souza, R.M.G.P. On-Line Monitoring of the IPR-R1 TRIGA Reactor Neutronic Parameters.
Progress in Nuclear Energy (New series), v. 52, p. 292-297, 2010. Elsevier Ltd. Editor T.D. Beynon, Oxford
UK. ISSN: 0149-1970. doi:10.1016/j.pnucene.2009.07.013. April 2010.
27.
Costa, A.L; Reis, P.A.L.; Pereira, C.; Veloso, M.A.F.; Mesquita, A.Z.; Soares, H.V. Thermal Hydraulic Analysis of
the IPR-R1 TRIGA Research Reactor Using a RELAP5 Model. Nuclear Engineering and Design (Print), v. 240, p.
1487-1494. Elsevier Ltd. Editor Y. A. Hassan. ISSN: 0029-5493. doi: 10.1016/j.nucengdes.2010.02.012. 2.
2010.
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Reis, P.A.L.; Lombardi Costa, A.; Pereira, C.; Veloso, M.A.F.; Mesquita, A.Z.; Soares, H.V.; Barros, G.P.
Assessment of a RELAP5 Model for the IPR-R1 TRIGA Research Reactor. Annals of Nuclear Energy, v. 37, p.
1341-1350. Elsevier Ltd. Editor S M. Ghiaasiaan. ISSN: 0306-4549 doi:10.1016/j.anucene.2010.05.013.
2010.
29.
Grossi, P.A.; Tello, C.C.O.; Mesquita, A.Z. IPR-R1 TRIGA Research Reactor Decommissioning IAEA Proceedings
Series STI/PUB/1460, International Radiation Protection Association (IRPA12), v. 1, p. 274-284, 2010.
30.
Mesquita, A.Z. Experimental Heat Transfer Analysis of the IPR-R1 TRIGA Reactor. International Atomic
Energy Agency (IAEA-CN-156). IAEA Publication - Research Reactors: Safe Management and Effective
Utilization, v. IAEA, p. 1-10. Vienna. ISSN: 1991-2374. 2008.
Mesquita, A.Z.; Rezende, H.C. Experimental Determination of Heat Transfer Coefficients in Uranium
Zirconium Hydride Fuel Rod. International Journal of Nuclear Energy, Science and Technology (Print), v. 3, p.
170-179. Inderscience Publishers Ltd. ISSN: 1741-6361. doi: 10.1504/IJNEST.2007.014654. 2007.
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Mesquita, A.Z.; Rezende, H.C. Thermal Behaviour of the IPR-R1 TRIGA Nuclear Reactor. International Journal
of Nuclear Energy, Science and Technology (Print), v. 3, p. 160-169. Inderscience Publishers Ltd. ISSN: 17416361. doi: 10.1504/IJNEST.2007.014653. 2007.
Mesquita, A.Z.; Rezende, H.C.; Tambourgi, E.B. Power Calibration of the TRIGA Mark I Nuclear Research
Reactor. Journal of the Brazilian Society of Mechanical Sciences and Engineering, v. XXIX, p. 240-245. Rio de
Janeiro. Editor C. R. Maliska. ISSN:1678-5878. doi: 10.1590/S1678-58782007000300002. 2007.
Mesquita, A.Z.; Rezende, H.C.; Tambourgi, E.B. Calibração da Potência do Reator Nuclear de Pesquisa TRIGA
IPR-R. Marzo 2005. Revista Iberoamericana de Ingeniería Mecánica, v. 9, n. 1, p. 37-45, 2005. Madrid.
Universidad Nacional de Educación a Distancia. Editor J. I. Pedrero. ISSN 1137-2729. 2005.
Mesquita, A.Z.; Rezende, H.C.; Tambourgi, E.B. Calibração da Potência do Reator Nuclear de Pesquisa TRIGA
IPR-R1, durante os Testes de Aumento de Potência de 100 kW para 250 kW. Research and Development
Brazilian Journal, Vol. 4 - No 2, Rio de Janeiro, Brazil v. 4, p. 285-290. ISSN 0104-7698. Setembro 2002.
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Centro de Desenvolvimento da Tecnologia Nuclear - CDTN
Comissão Nacional de Energia Nuclear - CNEN
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Mesquita, A.Z.; Ladeira, L.C.D. Dispositivo para Desencapar Termopares de Isolação Mineral, pela Remoção
de sua Blindagem por Corrente Elétrica. Revista de Propriedade Industrial, Rio de Janeiro, Brazil v. 1, p. 1515, 1987.
Articles Accepted in Scientific Journals:
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Pinto, A. J.; Mesquita, A.Z.; Tello, C.C.O.; Stehling, E.T. Sistema simulador da evolução do fluxo neutrônico em
reator nuclear de pesquisa, utilizando o software LabVIEW. Revista Tecnologia (UNIFOR), 2014.
Mesquita, A.Z.; Rezende, H.C.; Santos, A.A.C.; Silva, V.V.A. Development of Methods for Monitoring and
Controlling Power in Nuclear Reactors. Engenharia Térmica, 2014.
Palma, D.A.P.; Mesquita, A.Z.; Marinho, F.C.; Rocha, M.D.S. Evaluation of Nuclear Fuel Centerline Temperature
using New UO2 Thermal Conductivity Models. Journal of Energy and Power Engineering, 2014.
Proceedings of Conferences:
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Palma, D.A.P; Mesquita, A.Z.; Martinez A.S. Evaluation of Nuclear Fuel Centreline Temperature Using New UO2
Thermal Conductivity Models. In: LWR Fuel Performance Meeting / TopFuel 2013, Charlotte, NC. Proceedings of
LWR Fuel Performance Meeting / TopFuel 2013. La Grange Park, USA: American Nuclear Society - ANS Scientific
Publications Office, 2013.
Pinto, A.J.; Mesquita, A.Z.; Lameiras, F.S. Estudo de Parâmetros Operacionais Do Reator Nuclear De Pesquisa
Triga Ipr-R1 Utilizando Instrumentos Virtuais. In: 5 Congreso Internacional de Ingenierías Mecánica, Eléctrica,
Electrónica, Mecatrónica, Computaciónal y Diseño Industrial (5CIMEEM2013), Ciudad de México. Memorias del
5CIMEEM2013. Universidad Autónoma Metropolitana Unidad Azcapotzalco, 2013.
Rodrigues, R.R.; Mesquita, A.Z. Design of a System for Fuel Elements Cladding Inspection of a Nuclear Research
Reactor. In: 4th International Conference on Integrity, Reliability and Failure (IRF2013), Funchal/Madeira
(Portugal). Proceedings of IRF'2013. v. 1. p. 69-70. ISBN: 9789728826277. Porto: Faculty Engineering, University
of Porto, 2013.
Silva, V.V.A; Santos, A.A.C.; Silva, P.S.B.L.; Mesquita, A.Z.; Pereira, C. TRIGA Fuel Element Simulation Using
OpenFOAM. In: European Research Reactor Conference (RRFM 2013). Saint Petersburg, Russian. Transactions
of European Research Reactor Conference. European Nuclear Society (ENS). v. 1. p. 62-70. ISBN:
9789295064188. 2013.
Mesquita, A.Z.; Pinto, A.J.; Lameiras, F.S. TRIGA Reactor PC-Based Simulator for Training and Education. In:
Nuclear Education and Training (NESTet 2013), Madrid. Transactions of NESTet 2013. European Nuclear Society
(ENS), v. 1. p. 407-417. ISBN: 9789295064195. 2013.
Mesquita, A.Z.; Rezende, H.C.; Ferreira, A. V.; Dalle, H.M. Utilization of Brazilian Research Reactor TRIGA for
Education and Training. In: NESTet 2013 Nuclear Education and Training, Madrid. Transactions of NESTet 2013.
v. 1. p. 460-470. ISBN: 9789295064195. Brussels: European Nuclear Society (ENS), 2013.
Rodrigues, R.R.; Mesquita, A.Z. Sistema para Inspeção dos Elementos Combustíveis do Reator Nuclear de
Pesquisa TRIGA do Brasil. In: 11 Congreso Interamericano de Computación Aplicada a la Industria de Procesos
(CAIP'2013), Lima. Libro de Trabajos Completos del CAIP'2013,. Lima: La Pontificia Universidad Católica del
Perú, 2013.
Palma, D.A.P; Mesquita, A.Z.; Gonçalves, A.C.; Martinez A.S. Evaluation of Thermomechanical Behavior of
Nuclear Fuel Using the Codes CNFR and FRAPCON. In: 22nd International Congress of Mechanical Engineering
(COBEM 2013), Ribeirão Preto. COBEM 2013 - Engineering for Technology Innovation. Rio: Associação Brasileira
de Engenharia e Ciências Mecânicas (ABCM), ISBN: 1676-1790. 2013.
Rezende, H.C.; Mesquita, A.Z.; Santos, A.A.C.; Silva, V.V.A. Experiments in the Thermal Stratification Test
Facility at Nuclear Technology Development Center (CDTN). In: 22nd International Congress of Mechanical
Engineering (COBEM 2013), Ribeirão Preto. COBEM 2013 - Engineering for Technology Innovation. Rio:
Associação Brasileira de Engenharia e Ciências Mecânicas (ABCM), ISBN: 1676-1790. 2013.
Pinto, A. J.; Mesquita, A.Z.; Lameiras, F.S. Operational Parameters Study of IPR-R1 TRIGA Research Reactor
Using Virtual Instruments. In: 22nd International Congress of Mechanical Engineering (COBEM 2013), Ribeirão
Preto. COBEM 2013 - Engineering for Technology Innovation. Rio: Associação Brasileira de Engenharia e
Ciências Mecânicas (ABCM), ISBN: 1676-1790. 2013.
Reis, P.A.L.; Costa, A.L.; Pereira, C.; Veloso, M.A.F.; Soares, H.V. ; Mesquita, A.Z. Thermal Hydraulic Simulation
of the TRIGA IPR-R1 Using the RELAP5-3D. In: 22nd International Congress of Mechanical Engineering (COBEM
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Comissão Nacional de Energia Nuclear - CNEN
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2013), Ribeirão Preto. COBEM 2013 - Engineering for Technology Innovation. Rio: Associação Brasileira de
Engenharia e Ciências Mecânicas (ABCM), ISBN: 1676-1790, 2013.
Corrade, T.J.R. ; Mesquita, A.Z. ; Santos, A.A.C. . Development of Data Acquisition System for the Water-Air
Loop of the CDTN Thermal Hydraulic Laboratory. In: 22nd International Congress of Mechanical Engineering
(COBEM 2013), Ribeirão Preto. COBEM 2013 - Engineering for Technology Innovation. Rio: Associação Brasileira
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Nuclear Reactor Physics and Thermal Hydraulics (XVI ENFIR). Rio de Janeiro/Brazil. Brazilian Society of Nuclear
Engineering – ABEN. 2009. ISBN: 9788599141038.
Reis, P.A.L.; Costa, L.C.; Pereira, C.; Fortini, M.A.V.; Mesquita, A.Z.; Soares, H.V. Validation of a RELAP5 Model
for the IPR-R1 TRIGA Research Reactor. XVI Meeting on Nuclear Reactor Physics and Thermal Hydraulics (XVI
ENFIR), International Nuclear Atlantic Conference - INAC 2009. Rio de Janeiro/Brazil. Brazilian Society of
Nuclear Engineering - ABEN, 2009. ISBN: 9788599141038.
Mesquita, A.Z.; Souza, R.M.G.P.; Rezende, H.C. Thermal Power Calibrations of the IPR-R1 TRIGA Nuclear
Reactor. 20th International Congress of Mechanical Engineering - COBEM 2009, Gramado/Brazil. Brazilian
Society of Mechanical Sciences and Engineering - ABCM, 2009. ISBN: 21765480.
Mesquita, A.Z.; Cândido, M.A.; Pinto, A.J.; Dalle, H.M. Instrumented Fuel Element Recovery in IPR-R1 TRIGA
Nuclear Research Reactor. 20th International Congress of Mechanical Engineering - COBEM 2009,
Gramado/Brazil. Brazilian Society of Mechanical Sciences and Engineering - ABCM, 2009. ISBN: 21765480.
Mesquita, A.Z.; Costa, A.C.L.; Souza, R.M.G.P. Upgrading of the IPR-R1 TRIGA Nuclear Research Reactor
Instrumentation and Control. 20th International Congress of Mechanical Engineering - COBEM 2009,
Gramado/Brazil. Brazilian Society of Mechanical Sciences and Engineering - ABCM, 2009. ISBN: 21765480.
Pinto, A.J.; Mesquita, A.Z.; Tello, C.C.O. Supervisory System to Monitor the Neutron Flux of the IPR-R1 TRIGA
Research Reactor at CDTN. XVI Meeting on Nuclear Reactor Physics and Thermal Hydraulics (XVI ENFIR).
International Nuclear Atlantic Conference - INAC 2009. Rio de Janeiro/Brazil. Brazilian Society of Nuclear
Engineering - ABEN, 2009. ISBN: 9788599141038.
84)
Souza, R.M.G.P.; Mesquita, A.Z. Isothermal Temperature and Power Reactivity Coefficients Measured in IPR-R1
TRIGA Reactor. XVI Meeting on Nuclear Reactor Physics and Thermal Hydraulics (XVI ENFIR). International
Nuclear Atlantic Conference. Brazilian Society of Nuclear Engineering - ABEN, 2009. Rio de Janeiro/Brazil. ISBN:
9788599141038.
85)
Souza, R.M.G.P.; Mesquita, A.Z. Reactivity Measurements and Balance in the IPR-R1 TRIGA Reactor. XVI
Meeting on Nuclear Reactor Physics and Thermal Hydraulics (XVI ENFIR). International Nuclear Atlantic
Conference - INAC 2009. Rio de Janeiro/Brazil. Brazilian Society of Nuclear Engineering -ABEN, 2009. ISBN:
9788599141038.
Mesquita, A.Z.; Rezende, H.C., Souza, R.M.G.P. Thermal Power Calibrations of the IPR-R1 TRIGA Reactor by the
Calorimetric and the Heat Balance Methods. XVI Meeting on Nuclear Reactor Physics and Thermal Hydraulics
(XVI ENFIR). International Nuclear Atlantic Conference- INAC 2009. Rio de Janeiro. Brazilian Society of Nuclear
Engineering - ABEN, 2009. ISBN: 9788599141038.
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Comissão Nacional de Energia Nuclear - CNEN
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Mesquita, A.Z.; Rezende, H.C.; Souza, R.M.G.P. Comparação entre o Método Calorimétrico e o Método do
Balanço Térmico na Calibração da Potência do Reator Nuclear de Pesquisa TRIGA IPR-R1. 9º Congresso
Iberoamericano de Engenharia Mecânica - Cibim9, Las Palmas de Gran Canaria/Spain. Federação
Iberoamericana de Engenharia Mecânica - Feibim, v. I. p. 06-16. 2009. ISBN: 9788469285169.
88)
Mesquita, A.Z.; Pinto, A.J.; Cândido, M.A. Recuperação dos Termopares do Elemento Combustível
Instrumentado do Reator Nuclear TRIGA IPR-R1. 9º Congreso Iberoamericano de Ingeniería Mecánica - Cibim9.
Las Palmas de Gran Canaria/Spain: Federação Iberoamericana de Engenharia Mecânica - Feibim. v. 1. p. 64-74.
2009. ISBN: 9788469285169.
Costa, A.C.L.; Mesquita, A.Z.; Souza, R.M.G.P. Atualização da Instrumentação e do Controle do Reator Nuclear
de Pesquisa TRIGA IPR-R1. 9º Congreso Iberoamericano de Ingeniería Mecánica - Cibim9. Las Palmas de Gran
Canaria/Spain. Federação Iberoamericana de Engenharia Mecânica – Feibim. 2009, v. 1. p. 59-71. ISBN:
9788469285169.
Pinto, A.J.; Mesquita, A.Z.; Tello, C.C.O. Desenvolvimento de Sistema de Aquisição de Dados Usando LabVIEW
para Monitoraração da Potência do Reator de Pesquisa TRIGA IPR-R1. 9º Congreso Iberoamericano de
Ingeniería Mecánica -Cibim9. Las Palmas de Gran Canaria/Spain. Federação Iberoamericana de Engenharia
Mecânica – Feibim. 2009. v. 1. p. 72-81. ISBN: 9788469285169.
89)
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Mesquita, A.Z.; Rezende, H.C. Experimental Investigation of the Onset of Nucleate Boiling in the IPR-R1 TRIGA
Nuclear Research Reactor. 1º Encontro Brasileiro sobre Ebulição, Condensação e Escoamento Multifásico
Líquido-Gás - EBECEM 2008. Florianópolis. Universidade Federal de Santa Catarina, 2008.
Mesquita, A.Z.; Rezende, H.C. Avaliação Experimental da Convecção Natural e da Altura do Efeito Chaminé no
Reator Nuclear de Pesquisa TRIGA IPR-R1. V Brazilian Congress of Mechanical Engineering – CONEM 2008.
Universidade Federal da Bahia. Salvador/Brazil. Brazilian Society of Mechanical Sciences and Engineering ABCM. 2008.
93)
Mesquita, A.Z.; Souza, R.M.G.P. The Operational Parameter Electronic Database of the IPR-R1 TRIGA Research
Reactor. 4th World TRIGA Users Conference. TRIGA International, AREVA CERCA. Lyon / France. 2008.
94)
Grossi, P.A.; Toledo, C.C.O.; Mesquita, A.Z. IPR-R1 TRIGA Research Reactor Decommissioning Plan. 12th
International Congress of the International Radiation Protection Association (IRPA 12). Argentine Radiation
Protection Society (SAR). Buenos Aires/Argentine. 2008.
Mesquita, A.Z.; Souza, R.M.G.P., On-Line Measurement of the Reactivity Temperature Coefficient of the IPR-R1
TRIGA Nuclear Research Reactor. 12th Brazilian Congress of Thermal Engineering and Sciences - ENCIT 2008.
Brazilian Society of Mechanical Sciences and Engineering – ABCM. Belo Horizonte/Brazil. 2008. ISBN:
9788585769376.
95)
96)
Mesquita, A.Z.; Rezende, H.C. On Line System for Power Monitoring of the IPR-R1 TRIGA Reactor by Thermal
Methods. International Nuclear Atlantic Conference - INAC 2007. Brazilian Society of Nuclear Engineering –
ABEN. Santos/Brazil. 2007. v. 1. ISBN: 9788599141021.
97)
Mesquita, A.Z.; Souza, R.M.G.P. On Line Monitoring of the Reactivity and Control Rods Worth at the IPR-R1
TRIGA Reactor. International Nuclear Atlantic Conference - INAC 2007. Brazilian Society of Nuclear Engineering
– ABEN. Santos/Brazil. 2007. v. 1. ISBN: 9788599141021.
Cândido, M.A.; Mesquita, A.Z. ; Costa, A.C.L. Construction of the Monitoring, Processing and Logging System for
the IPR-R1 TRIGA Nuclear Reactor. International Nuclear Atlantic Conference - INAC 2007. Brazilian Society of
Nuclear Engineering – ABEN. Santos/Brazil. 2007. v. 1. ISBN: 9788599141021.
98)
99)
Souza, R.M.G.P.; Mesquita, A.Z. The Brazilian IAEA Expert Missions in the Recommissioning of the IAN-R1 TRIGA
Research Reactor. International Nuclear Atlantic Conference – INAC 2007. Brazilian Society of Nuclear
Engineering – ABEN. Santos/Brazil. 2007. v. 1. ISBN: 9788599141021.
100)
Toledo, C.C.O.; Grossi, P.A.; Mesquita, A.Z. IPR-R1 TRIGA Research Reactor Decommissioning: Preliminary Plan.
International Nuclear Atlantic Conference – INAC 2007. Brazilian Society of Nuclear Engineering – ABEN.
Santos/Brazil. 2007. v. 1. ISBN: 9788599141021.
101)
Ricardo, C.P.; Mesquita, A.Z. Sistema de Monitoração em Tempo Real das Variáveis de Operação do Reator
Nuclear de Pesquisa TRIGA IPR-R1. International Nuclear Atlantic Conference, Santos. INAC 2007. Brazilian
Society of Nuclear Engineering – ABEN. Santos/Brazil. 2007. v. 1. ISBN: 9788599141021.
102)
Ricardo, C.P.; Mesquita, A.Z. Criação do Banco de Dados Eletrônico das Operações do Reator TRIGA IPR R1. In:
14a. Jornada Nacional de Iniciação Científica, 2007, Belém, Brazil. 59ª Reunião Anual da SBPC, 2007.
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Mesquita, A.Z. ; Rezende, H.C. Canais de Medida de Potência do Reator Nuclear de Pesquisa TRIGA IPR-R1 por
Processos Térmicos. 8vd. Congreso Iberoamericano de Ingeniería Mecánica - CIBIM 8. Pontifica Universidad
Católica del Perú, Lima. Cusco - Perú 2007. ISBN: 97899722885.
Mesquita, A.Z.; Rezende, H.C. Power Measure Channels of the IPR-R1 TRIGA Research Nuclear Reactor by
Thermal Methods. 19th International Congress of Mechanical Engineering – COBEM 2007. Brazilian Society of
Mechanical Sciences and Engineering – ABCM. Brasília/Brazil. 2007. ISBN: 9788585769345.
Mesquita, A.Z. Experimental Heat Transfer Analysis of the IPR-R1 TRIGA Reactor. International Conference on
Research Reactors: Safe Management and Effective Utilization. International Atomic Energy Agency (IAEA).
Sydney/Australia. 2007.
Mesquita, A.Z.; Souza, R.M.G.P. System for Monitoring the IPR-R1 TRIGA Reactor Parameters. International
Workshop on Research Reactor Utilization: 50 Years of the Safe and Sustainable Operation of the IEA-R1
Research Reactor. Institute of Nuclear and Energy Research (IPEN). São Paulo/Brazil. 2007.
107)
Mesquita, A.Z.; Rezende, H.C. Experimental Investigation of Heat Transfer Coefficients on the TRIGA IPR-R1
Nuclear Reactor Fuel Rods. ECI International Conference on Boiling Heat Transfer, Spoleto/Italy. 2006.
108)
Mesquita, A.Z.; Rezende, H.C. Experimental Investigation of Temperature Patterns in the IPR-R1 TRIGA Nuclear
Reactor. 3rd World TRIGA Users Conference. Centre of Nuclear Technology Development (CDTN). Belo
Horizonte/Brazil. 2006.
109)
Mesquita, A.Z.; Rezende, H.C. Experimental Heat Transfer Analysis of the IPR-R1 TRIGA Reactor. 3rd World
TRIGA Users Conference. Centre of Nuclear Technology Development (CDTN). Belo Horizonte/Brazil. 2006.
Mesquita, A.Z.; Rezende, H.C. Experimental Prediction of the Critical Heat Flux on the IPR-R1 TRIGA Nuclear
Reactor. 3rd World TRIGA Users Conference. Centre of Nuclear Technology Development (CDTN). Belo
Horizonte/Brazil. 2006.
110)
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Mesquita, A.Z.; Souza, R.M.G.P.; Rivero, T. IAEA Expert Mission in the Recommissioning of the IAN-R1 TRIGA
Research Reactor. 3rd World TRIGA Users Conference. Centre of Nuclear Technology Development (CDTN).
Belo Horizonte/Brazil. 2006.
112)
Souza, R.M.G.P.; Mesquita, A.Z.; Castiblanco L.A. Hot Commissioning Tests and Technical Results of the IAN-R1
TRIGA Reactor. 3rd World TRIGA Users Conference. Centre of Nuclear Technology Development (CDTN). Belo
Horizonte/Brazil. 2006.
113)
Mesquita, A.Z.; Souza, R.M.G.P.; Maretti J.F.; Oliveira, P.F.; Câmara, L.O.I.S. Operational Parameter Behavior of
the IPR-R1 TRIGA Mark 1 Reactor. 3rd World TRIGA Users Conference. Centre of Nuclear Technology
Development (CDTN). Belo Horizonte/Brazil. 2006.
Cândido, M.A.; Mesquita, A.Z.; Costa, A.C.L. Building a Data Acquisition System Upgrade for the IPR-R1 TRIGA
Nuclear Reactor. 3rd World TRIGA Users Conference. Centre of Nuclear Technology Development (CDTN). Belo
Horizonte/Brazil. 2006.
114)
115)
Costa, A.C.L.; Mesquita, A.Z. Uncertainty Analysis on Thermohydraulic Parameters of the IPR-R1 TRIGA Research
Reactor. 3rd World TRIGA Users Conference. Centre of Nuclear Technology Development (CDTN). Belo
Horizonte/Brazil. 2006.
116)
Souza, R.M.G.P.; Mesquita, A.Z.; Maretti Jr, F.; Oliveira, P.F.; Câmara, L.O.I.S. Reactivity Power Coefficient
Determination of the IPR-R1 TRIGA Reactor. 3rd World TRIGA Users Conference. Centre of Nuclear Technology
Development (CDTN). Belo Horizonte/Brazil. 2006.
117)
Alencar, D.A.; Silva Júnior, S.F.; Mesquita, A.Z.; Câmara, L.O.I.S; Oliveira, P.F. Using Visual Inspection Ndt To
Check Integrity Of Triga Mark I Fuel Rods. 3rd World TRIGA Users Conference. Centre of Nuclear Technology
Development (CDTN). Belo Horizonte/Brazil. 2006.
118)
Ricardo, C.P.; Mesquita, A.Z. Resultados Preliminares da Investigação Experimental da Evolução dos Parâmetros
de Operação do Reator Nuclear de Pesquisa TRIGA IPR-R1. XII Seminário Anual Programa Institucional De Bolsas
de Iniciação Científica CNPq – PIBIC. Brazilian Council for Scientific and Technological Development (CNPq). São
Paulo/Brazil. 2006.
119)
Ricardo, C.P.; Mesquita, A.Z. Investigação da Evolução dos Parâmetros de Operação do Reator Nuclear de
Pesquisa TRIGA IPR-R1 com Variação de Potência em Degraus. Seminário Anual de Iniciação Científica do CDTN.
Centre of Nuclear Technology Development (CDTN). Belo Horizonte/Brazil. 2006.
120)
Costa, A.C.L.; Mesquita, A.Z.; Rezende, H.C. Análise de Incerteza Aplicada a Parâmetros Termo-Hidráulicos do
Reator Nuclear de Pesquisa TRIGA IPR-R1. 11th Brazilian Congress of Thermal Sciences and Engineering - ENCIT
2006, Curitiba/Brazil. 2006.
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Rezende, H.C.; Mesquita, A.Z. Experimental Prediction of Departure from Nucleate Boiling on the IPR-R1 TRIGA
Nuclear Reactor Core. 11th Brazilian Congress of Thermal Sciences and Engineering -- ENCIT 2006. Brazilian
Society of Mechanical Sciences and Engineering – ABCM. Curitiba/Brazil. 2006.
Mesquita, A.Z.; Rezende, H.C. Experimental Thermal-Hydraulic Analysis of the IPR-R1 TRIGA Nuclear Reactor.
11th Brazilian Congress of Thermal Sciences and Engineering - ENCIT 2006. Brazilian Society of Mechanical
Sciences and Engineering – ABCM. Curitiba/Brazil. 2006.
Alencar, D.A., Silva Júnior, S.F., Mesquita, A.Z., Câmara, L.O.I.S, Oliveira, P.F. Using Visual Inspection NDT to
Check Integrity of TRIGA Mark I Fuel Rods In: 3nd World TRIGA Users Conference, Belo Horizonte/Brazil. 2006.
124)
Mesquita, A.Z.; Rezende, H.C.; Costa, A.C.L. Experimental Investigation of the Temperature Distribution on the
TRIGA IPR-R1 Research Nuclear Reactor and Development of Power Measuring Channels by Thermal Processes.
18th International Congress of Mechanical Engineering – COBEM 2005. Brazilian Society of Mechanical Sciences
and Engineering – ABCM. Ouro Preto/Brazil. 2005.
125)
Mesquita, A.Z.; Rezende, H.C. Levantamento de Temperaturas e Coeficientes de Transferência de Calor no
Reator Nuclear de Pesquisa TRIGA IPR-R1. 7o. Congreso Iberoamericano de Ingenieria Mecanica. Federação
Iberoamericana de Engenharia Mecânica – Feibim. México DF/México. 2005. ISBN: 9703602940.
126)
Mesquita, A.Z., Rezende, H.C. Data Acquisition System for TRIGA Mark I Nuclear Reactor and a Proposal for Its
Automatic Operation In: INAC 2005-International Nuclear Atlantic Conference/XIV ENFIR-National Meeting of
Reactor Physics and Thermal Hydraulics, 2005, Santos. INAC 2005. Brazilian Society of Nuclear Engineering –
ABEN, 2005.
127)
Mesquita, A.Z., Rezende, H.C., Costa, A.C.L. Experimental Determination of Heat Transfer Coefficients in
Uranium Zirconium Hydride Fuel Rod. In: INAC 2005-International Nuclear Atlantic Conference/XIV ENFIRNational Meeting of Reactor Physics and Thermal Hydraulics, 2005, Santos. INAC 2005. Brazilian Society of
Nuclear Engineering – ABEN, 2005.
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Mesquita, A.Z., Rezende, H.C., Costa, A.C.L. Experimental Investigation of the Temperature Distribution on the
TRIGA IPR-R1 Research Nuclear Reactor and Development of Power Measuring Channels by Thermal Processes.
In: 18th International Congress of Mechanical Engineering - COBEM2005, 2005, Ouro Preto.
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International Congress of Mechanical Engineering - COBEM2005. Ouro Preto: 18th International Congress of
Mechanical Engineering - COBEM2005, 2005.
Mesquita, A.Z., Rezende, H.C. Levantamento de Temperaturas e Coeficientes de Transferência de Calor no
Reator Nuclear de Pesquisa TRIGA IPR-R1. In: 7o. Congreso Iberoamericano de Ingenieria Mecanica, 2005,
Cidade do México. 7o. Congreso Iberoamericano de Ingenieria Mecanica. Cidade do México: 7o. Congreso
Iberoamericano de Ingenieria Mecanica, 2005.
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Maretti J., F., Mesquita, A.Z., Oliveira, P. F., Câmara, L. O. I. S, Dale, H M. Performance and Improvements of the
IPR-R1 TRIGA Mark I Reactor In 45 Years of Operation. In: INAC 2005-International Nuclear Atlantic
Conference/XIV ENFIR-National Meeting of Reactor Physics and Thermal Hydraulics, 2005, Santos. INAC 2005.
Brazilian Society of Nuclear Engineering – ABEN, 2005.
Mesquita, A.Z., Rezende, H.C., Maretti J., F., Oliveira, P. F., Câmara, L.O.I.S. Thermal Behaviour of the IPR-R1
TRIGA Nuclear Reactor. In: INAC 2005-International Nuclear Atlantic Conference/XIV ENFIR-National Meeting of
Reactor Physics and Thermal Hydraulics, 2005, Santos. INAC 2005. Brazilian Society of Nuclear Engineering –
ABEN, 2005.
Mesquita, A.Z. Advanced Nuclear Research Reactor In: Americas Nuclear Energy Symposium (ANES) 2004, 2004,
Miami Beach - Florida. Americas Nuclear Energy Symposium (ANES) 2004. La Grange Park, Illinois: American
Nuclear Society, 2004.
Mesquita, A.Z., Rezende, H.C., Maretti J., F., Tambourgi, E. B. Data Acquisition and Signal Processing System for
IPR R1 TRIGA Mark I Nuclear Research Reactor of CDTN. In: 2nd World TRIGA Users Conference, 2004, Vienna.
2nd World TRIGA Users Conference, 2004.
Mesquita, A.Z., Rezende, H.C., Maretti Jr, F., Tambourgi, E.B. Data Acquisition System forTRIGA Mark I Nuclear
Research Reactor of CDTN. In: America Nuclear Energy Symposium (ANES 2004), 2004, Miami Beach, Florida.
America Nuclear Energy Symposium - ANES 2004, 2004.
Mesquita, A.Z., Rezende, H. C., Tambourgi, E. B. Calibração da Potência do Reator Nuclear de Pesquisa TRIGA
IPR-R1. In: VI Congresso Ibero Americano de Energia Mecânica - Cibem6, 2003, Coimbra. Livro de Actas do
Cibem6. Coimbra/Portugal: Gráfica de Coimbra, 2003. v.II. p.1355 – 1360.
Mesquita, A.Z., Rezende, H.C., Tambourgi, E. B. Power Calibration of the TRIGA Mark I Nuclear Research
Reactor. In: 17th International Congress of Mechanical Engineering, 2003, São Paulo, Brazil. Brazilian Society of
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Mesquita, A.Z., Maretti J., F. The Uses of the Dilatation Method in the Detection of the Critical Heat Flux in
Nuclear Simulated Fuel Elements. In: 17th International Congress of Mechanical Engineering, São Paulo. São
Paulo, Brazil: Brazilian Society of Mechanical Engineering, 2003.
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Mesquita, A.Z., Rezende, H. C. Calibração da Potência do Reator TRIGA IPR-R1 durante os Testes de Aumento de
Potência para 250 kW. In: INAC-International Nuclear Atlantic Conference/XIII ENFIR-National Meeting of
Reactor Physics and Thermal Hydraulics, Rio de Janeiro, Brazil. INAC 2002 Papers. Brazilian Society of Nuclear
Engineering – ABEN, 2002.
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Mesquita, A.Z., Maretti J., F. Temperature Distribution at the Pool and the Core of the IPR-R1 TRIGA Mark 1
Reactor. In: 1st. Word TRIGA Users Conference, 2002, Pavia. 1st. TRIGA Users Conference. Pavia: Universitá
Deglistudi di Pavia, 2002.
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Mesquita, A.Z., Rezende, H. C. Thermal Power Calibration of the TRIGA Mark 1 IPR-R1 Reactor during the
Upgrading Tests to 250 kW. In: 1st. Word TRIGA Users Conference, Pavia. 1st. Word TRIGA Users Conference,
Universitá Deglistudi de Pavia, LENA, June 16-20, 2002. Universitá Deglistudi de Pavia, 2002.
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Mesquita, A.Z. Temperature Mapping in the Research Reactor IPR-R1 TRIGA Mark I. In: 1st. Word TRIGA Users
Conference, 2001, Pavia/Italy. Proceeding of 1st. Word TRIGA Users Conference. Pavia: Universitá Deglistudi de
Pavia, LENA, 2001.
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Mesquita, A.Z. Mapeamento de Temperatura do Reator TRIGA IPR-R1. In: XII Encontro Nacional de Física de
Reatores e Termohidráulica., 2000, Rio de Janeiro. XII Encontro Nacional de Física de Reatores e
Termohidráulica.. Rio de Janeiro: Brazilian Society of Nuclear Engineering – ABEN. 2000.
Cruz, J. R. B., Mesquita, A.Z., Rocha, Z., Oliveira, P. F., Rodrigues, R.R. Programa de Gestão de Envelhecimento
para o Reator TRIGA IPR-R1. In: XII Encontro Nacional de Física de Reatores e Termohidráulica., Rio de Janeiro.
XII Encontro Nacional de Física de Reatores e Termohidráulica.. Rio de Janeiro: Brazilian Society of Nuclear
Engineering – ABEN, 2000.
Mesquita, A.Z., Rezende, H.C. Infra-Estrutura do Laboratório de Termohidráulica do CDTN para Calibração de
Temperatura e Pressão. In: Encontro Nacional de Física de Reatores e Termohidráulica, 1997, Poços de Caldas.
Encontro Nacional de Física de Reatores e Termohidráulica. Rio de Janeiro: Brazilian Society of Nuclear
Engineering – ABEN, 1997.
Mesquita, A.Z., Ladeira, L. C. D. Dispositivo para Recuperação de Termopares. In: IV Simpósio Regional de
Instrumentação - I Congresso Mineiro de Automação, 1996, Belo Horizonte. Anais do IV Simpósio Regional de
Instrumentação - I Congresso Mineiro de Automação. Belo Horizonte: Grupo de Instrumentação de Minas
Gerais - GRINST - MG, 1996. v.1. p.46 - 48
Mesquita, A.Z. Equipamento para Recuperação de Termopares de Isolação Mineral pela Remoção de sua
Blindagem por Corrente Elétrica In: VI Congresso Geral de Energia Nuclear, Rio de Janeiro. Anais do VI CGEN.
Rio de Janeiro: Brazilian Society of Nuclear Engineering – ABEN, 1996. v.1.
Mesquita, A.Z. Testes em Esquemas de Pintura das Superfícies de Aço Carbono da Esfera de Contenção sob
Condições de Acidente Base de Projeto In: X Encontro Nacional de Física de Reatores e Termohidráulica - X
ENFIR, Äguas de Lindóia. Anais do X ENFIR. Rio de Janeiro: ABEN - Associação Brasileira de Energia Nuclear,
1995. v.1. p.325 - 330
Mesquita, A.Z. Detecção de Fluxo de Calor Crítico em Varetas Simuladoras de Combustível Nuclear pelo Método
da Dilatação. In: IX Encontro Nacional de Física de Reatores e Termohidráulica, Caxambú. Anais do IX ENFIR.
Belo Horizonte: Centro de Desenvolvimento da Tecnologia Nuclear, 1993. v.1. p.327 – 330.
Mesquita, A.Z. Testes de Testes de Componentes de Fabricação Nacional para Usinas Nucleares sob Condições
de um Acidente Base de Projeto. In: 3o. Congresso Geral de Energia Nuclear. Rio de Janeiro. Anais do 3o. CGEN.
Rio de Janeiro: Brazilian Society of Nuclear Engineering – ABEN, 1990. v.1.
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