Livros publicados/organizados ou edições
1.
MESQUITA, A. Z.. Energia Nuclear: Uma Introdução. ISBN: 9788584802210. . https://www.editora.ufpr.br/produto/512/energia-nuclear--uma-introducao. 1. ed. Curitiba (PR): Editora UFPR - Universidade Federal do Paraná, 2023. v. 1. 249p .
2.
MATA, J.F.C. ; MESQUITA, A.Z. . Análise Probabilística de Acidentes no Licenciamento de Reatores Nucleares - Desenvolvimento de metodologia para análise probabilística de segurança aplicada ao licenciamento de reatores. ISBN-13: : 978-6202562461. 1. ed. Riga Letónia, União Europeia: KS OmniScriptum Publishing. Novas Edições Acadêmicas, 2020. v. 1. 164p .
3.
MESQUITA, A.Z.. Instrumento Digital para Testes por Correntes Parasitas. ISBN: 9786139611027. 1. ed. Riga Latvia: Novas Edições Acadêmicas. SIA OmniScriptum Publishing, 2018. v. 1. 116p .
4.
MESQUITA, A.Z.. Termo-Hidráulica Experimental de Reator Nuclear de Pesquisa TRIGA. ISBN: 9783841715210. 1. ed. Saarbrücken - Alemanha: Novas Edições Acadêmicas - OmniScriptum GmbH & Co. KG, 2015. v. 1. 184p .
5.
Mesquita, Amir. Current Research in Nuclear Reactor Technology in Brazil and Worldwide. 1. ed. Rijeka: InTech, 2013. v. 1. 336p .
6.
Mesquita, Amir. Nuclear Reactors. 1. ed. Rijeka/Croatia: InTech, 2012. v. 1. 338p .
7.
MESQUITA, A.Z.; PINTO, A. J. ; Tello, C.C.O. ; LAMEIRAS, F.S. . DIGITAL CONTROL SYSTEM SIMULATION FOR NUCLEAR REACTOR NEUTRONIC PARAMETERS. ISBN: 978.1.61942.132.5.2012. 1. ed. Hauppauge, New York, NY/USA: Nova Science Publishers Inc., 2012. v. 1. 56p
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Artigos completos publicados em periódicos
1.
GOLVEIA SILVA, W. ; MESQUITA, A.Z. ; SILVA, M. J. ; VARELLA, L. Y. Z. ; ALVES, V. E. A. E. ; ALMEIDA, T. C. S. . TiO- nanotubular surface functionalization with rosmarinic acid and chitosan: a comparative study of immersion and electrodeposition methods. CADERNOS CAJUÍNA, v. 11, p. e2046, 2026.
2.
ALVES, VALÉRIA EMILIANA ; PEREIRA, BRUNO JOSÉ ALVES ; Mesquita, Amir Zacarias ; DE ALMEIDA, VITOR FERNANDES ; FERREIRA, LADISLAU MIRANDA ; PEDERSOLI, MARINA TAVARES E SILVA ; RIBEIRO, PATRÍCIA ALBERNÁZ MELO . A TECHNICAL-REGULATORY FRAMEWORK FOR INTEGRATING PHOTOVOLTAIC SYSTEMS INTO MINE CLOSURE PLANS (PFM) IN BRAZILUN MARCO TÉCNICO-REGULATORIO PARA LA INTEGRACIÓN DE SISTEMAS FOTOVOLTAICOS EN PLANES DE CIERRE DE MINAS (PFM) EN BRASILUM MARCO TÉCNICO-REGULATÓRIO PARA A INTEGRAÇÃO DE SISTEMAS FOTOVOLTAICOS EM PLANOS DE FECHAMENTO DE MINA (PFM) NO BRASIL. REVISTA DE GEOPOLITICA, v. 17, p. e2041, 2026.
3.
ALMEIDA, V. F. ; MESQUITA, A. Z. ; LEAL, A. S. ; SANTOS, F. S. ; PEREIRA, R. V. ; ALVES, V. E. A. E. ; FELIPPE, A.A.M ; BALIZA, A.R. ; VARELLA, L. Y. Z. ; GOLVEIA SILVA, W. . Utilization of Multimedia Resources in Nuclear Sciences Communication within the Brazilian School Environment.. BRAZILIAN JOURNAL OF RADIATION SCIENCES, v. 124B, p. 1-15, 2025.
4.
VARELLA, L. Y. Z. ; MESQUITA, A.Z. ; REZENDE, D. B. ; CREN, E. C. ; ALMEIDA, V. F. ; GOLVEIA SILVA, W. . Pretreatment of Biomass with Gamma Rays and Electron Beam for Ethanol Production via Enzymatic Hydrolysis: A Brief Review. BRAZILIAN JOURNAL OF RADIATION SCIENCES, v. 12(4A), p. 1-16, 2025.
5.
MESQUITA, A.Z.; LIMA, W. N. ; VARELLA, L. Y. Z. ; GOLVEIA SILVA, W. . Advancements and Challenges in Nuclear Fusion Reactors Technology: A Comprehensive Overview. Nuclear Fission Energy - Carbon Net Zero, Sustainability and Energy Availability, v. 1, p. 1-13, 2025.
6.
ALVES, VALÉRIA EMILIANA ALCÂNTARA E ; Mesquita, Amir Zacarias ; ALMEIDA, VITOR FERNANDES DE . Nuclear Licensing In Brazil. RGSA (ANPAD), v. 19, p. e011971, 2025.
7.
CAMARANO, D. M. ; VILELA, J. J. ; MESQUITA, A.Z. ; SILVA, E. C. E. . IPR-R1 Triga Reactor aging management approach . BRAZILIAN JOURNAL OF RADIATION SCIENCES, v. 12, p. e2670, 2025.
8.
FONSECA, LORENA ; CALHEIRO, DANIEL SILVA ; Mesquita, Amir ; ALONSO, THÊSSA ; SQUAIR, PETERSON . Calibração e avaliação do dosímetro MTS-N para a medição da dose absorvida em componentes sanguíneos. BRAZILIAN JOURNAL OF RADIATION SCIENCES, v. 12, p. e2502, 2025.
9.
MESQUITA, A.Z.; VARELLA, L. Y. Z. ; GOLVEIA SILVA, W. ; NUNES LIMA, W. ; ALONSO, T. C. . A little about nuclear fusion. BRAZILIAN JOURNAL OF RADIATION SCIENCES, v. 12, p. e2509, 2025.
10.
SENARIO FELIX, BIANCA ; SILVA CALHEIRO, DANIEL ; ZACARIAS MESQUITA, AMIR ; CRISTINA ALONSO, THESSA ; CORDEIRO LOPES, RENATA ; ALONSO, MARIANA NATIVIDADE . Brazilian and international legislation applied to food irradiation: a historical review. BRAZILIAN JOURNAL OF RADIATION SCIENCES, v. 13, p. e2827-e2842, 2025.
11.
FERREIRA, ISABELLA LELLIS ; BARROS, MARIA RITA PASCOAL DE SOUZA ; FONSECA, LORENA SOARES ; Mesquita, Amir Zacarias ; ALONSO, THÊSSA CRISTINA ; SANTANA, PRISCILA DO CARMO ; OLIVEIRA, PAULO MÁRCIO CAMPOS DE ; CALHEIRO, DANIEL SILVA . Verification of absorbed dose in blood component cases using radiochromic film EBT3. BRAZILIAN JOURNAL OF RADIATION SCIENCES, v. 13, p. e2830, 2025.
12.
OLIVEIRA, A. M. ; GONCALVES, L. M. ; GOMIDES, L. M. ; MESQUITA, A.Z. ; MAGOSSE, G. B. . THERMAL CHARACTERIZATION OF PLA, ABS, PETG, AND NYLON FILAMENTS FOR 3D PRINTING APPLICATIONS. ARACÊ - DIREITOS HUMANOS EM REVISTA, v. 7, p. 35702-35707, 2025.
13.
NUNES LIMA, W. ; MESQUITA, A.Z. ; GUIMARAES, M. C. ; PALMA, D.A.P ; ALONSO, T. C. . PROPOSAL FOR THE USE OF THORIUM AS FUEL AND ZIRCONIUM ALLOY CLADDING FOR TRIGA®-TYPE NUCLEAR RESEARCH REACTORS. RGSA (ANPAD), v. 19, p. 1-14, 2025.
14.
GONCALVES, L. M. ; OLIVEIRA, A. M. ; MESQUITA, A. Z. ; FERREIRA, D. J. O. ; MICHEL, H. C. C. . COMPUTATIONAL MATHEMATICAL MODELING OF AIRFLOW IN A CABIN-TYPE SOLAR DRYER USED FOR DRYING SUGAR CANE BAGASSE. RGSA (ANPAD), v. 19, p. 1-13, 2025.
15.
MACEDO, L. G. S. ; MESQUITA, A. Z. ; GUIMARAES, M. C. ; MEIRELES, L. S. ; ALONSO, T. C. ; CALHEIRO, D. S. . Experimental Survey of the Relationship Between Absorbed Dose and the Vertical Position of Samples in a Panoramic Gamma Irradiator. RGSA (ANPAD), v. 19, p. 1-12, 2025.
16.
ALCÂNTARA E ALVES, VALÉRIA EMILIANA ; LEIBING SARNEY, DANIEL JOSÉ ; Mesquita, Amir Zacarias ; FERNANDES, VITOR ; BALIZA, ANA ROSA . Should Brazil invest in Small Modular Reactor?Deveria o Brasil investir em Pequenos Reatores Nucleares? . BRAZILIAN JOURNAL OF RADIATION SCIENCES, v. 12, p. e2570, 2025.
17.
MESQUITA, A.Z.; PALMA, D.A.P ; ALMEIDA, V. F. . Experimental study of temperature distribution and development of a power monitoring channel for the IPR-R1 TRIGA® research nuclear reactor. NUCLEAR ENGINEERING AND DESIGN, v. 417, p. 112869, 2024. Citações:1|1
18.
VARELLA, LEONARDO Y.Z. ; Mesquita, Amir Z. ; DE REZENDE, DANIEL B. ; MOURÃO, ISABEL G. ; CREN, ÉRIKA C. ; LOPES, NILVA P. ; SILVA, WALEWSKA G. ; ALONSO, THESSA C. . Experimental evaluation of the use of gamma radiation in sugarcane bagasse (Saccharum spp.) as a pretreatment for bioethanol production. RADIATION PHYSICS AND CHEMISTRY, v. 219, p. 111611-111625, 2024. Citações:7
19.
ANTONIO C. LIMA, MARCO ; HENRICE, EDSON ; PALMA, DANIEL A.P. ; ZACARIAS MESQUITA, AMIR . Critical configuration of a SMR based on CAREM 25 using the SERPENT code. NUCLEAR ENGINEERING AND DESIGN, v. 423, p. 113192-7, 2024. Citações:3|2
20.
MARQUES dos SANTOS, A. M. ; MESQUITA, A.Z. ; SEBASTIAO, R. C. ; FONSECA, T. C. F. . Feasibility of new polymeric matrices in the production of ferrous sulphate dosimeters. APPLIED RADIATION AND ISOTOPES, p. 111526, 2024. Citações:1
21.
OLIVEIRA, A.M. ; MESQUITA, A. Z. ; MARQUES, J. G. O. ; BANDARRA FILHO, E. P. ; PALMA, D.A.P . Experimental Evaluation of Thermal Conductivity and Other Thermophysical Properties of Nanofluids Based on Functionalized (-OH) Mwcnt Nanoparticles Dispersed in Distilled Water. ADVANCES IN NANOPARTICLES, v. 12, p. 32-52, 2023.
22.
Mesquita, Amir Zacarias; PALMA, DANIEL ARTUR PINHEIRO ; SOUSA, ANNA ; SILVA, ELLEN DE OLIVEIRA . UMA IMPRESSÃO ACERCA DO PROGRAMA NUCLEAR BRASILEIRO SEGUNDO O IAEA SERVICES SERIES NG-G-3.1: AVALIAÇÃO DA PERDA DE CONHECIMENTO INDIVIDUAL NO ÓRGÃO REGULADOR BRASILEIRO. FOCO (FACULDADE NOVO MILÊNIO), v. 16, p. e1071, 2023.
23.
NATIVIDADE, M. A. ; ALONSO, T. C. ; MESQUITA, A.Z. . Regulation and supervision of food irradiation. BRAZILIAN JOURNAL OF RADIATION SCIENCES, v. 11, p. 1-10, 2023.
24.
FELIPPE, A.A.M ; LAGE, A.M.F. ; MESQUITA, A. Z. . Levantamento das expressões numéricas das variáveis de operação do reator nuclear triga IPR-R1 para sua simulação numérica. STUDIES IN ENVIRONMENTAL AND ANIMAL SCIENCES, v. 4, p. 160-167, 2023.
25.
SANTOS, ÂNGELA MOREIRA MARQUES DOS ; SEBASTIÃO, RITA DE CÁSSIA DE OLIVEIRA ; Mesquita, Amir Zacarias ; ALONSO, THÊSSA CRISTINA ; MANTUANO, ANDREA ; FONSECA, TELMA CRISTINA FERREIRA . Dose response assessment of conventional Fricke: a relationship between UV-Visible and nuclear magnetic resonance techniques. BRAZILIAN JOURNAL OF RADIATION SCIENCES, v. 11, p. 1-13, 2023.
26.
MARQUES, J. G. O. ; MESQUITA, A.Z. ; CAMPOLINA, D.A.M. ; CAMARANO, D. M. ; VILELA, J. J. ; LEAL, A. S. . Water quality management program for IPR-R1 TRIGA® research reactor. BRAZILIAN JOURNAL OF RADIATION SCIENCES, v. 11, p. 1-16, 2023.
27.
MESQUITA, A.Z.; OLIVEIRA, A.M. ; GONCALVES, L. M. ; REIS, I. C. . Avaliação experimental da eficiência do boro no controle da reatividade dos reatores nucleares refrigerados a água. RESEARCH, SOCIETY AND DEVELOPMENT, v. 11, p. 1-11, 2022.
28.
BALIZA, A.R. ; MESQUITA, A.Z. ; MORGHI, Y. . REVIEW OF CLAUSES FOR IMPLEMENTING AN ENVIRONMENTAL MANAGEMENT SYSTEM IN ACCORDANCE WITH THE ISO 14001:2015 FOR THE IPR-R1 TRIGA REACTOR OF CDTN. Brazilian Journal of Development (BJD), v. 8, p. 4122-4133, 2022.
29.
MESQUITA, A.Z.; Palma, D. A. P. ; OLIVEIRA, A.M. . Development of an Electronic Instrument for Eddy Current Testing. International Journal of Electrical and Computer Engineering Research, v. 2, p. 21-28, 2022.
30.
BALIZA, A.R. ; MESQUITA, A. Z. ; OLIVEIRA, A.M. ; GOMES DAVI, S. ; SANTOS, A. M. M. ; Palma, D. A. P. . Evaluation of the aging management system for the Triga research nuclear reactor in Brazil. Brazilian Journal of Development, v. 8, p. 23598-23607, 2022.
31.
SILVA, EDSON PEREIRA DA ; SOARES, CARLOS MANOEL DE ASSIS ; Mesquita, Amir Zacarias ; MENDES, BRUNO MELO . MODELING AND VALIDATION OF THE RDS-80A SURFACE CONTAMINATION METER WITH BETA EMITTING SOURCES USING MCNP6 AND GEANT4. Journal of Engineering Research, v. 2, p. 2-6, 2022.
32.
OLIVEIRA MARQUES, JOÃO GABRIEL ; Mesquita, Amir Zacarias ; LOMBARDI COSTA, ANTONELLA ; Pereira, Claubia . Methodology for Management and Physicochemical Control of the Cooling Water of the IPR-R1 Triga Nuclear Research Reactor. BRAZILIAN JOURNAL OF RADIATION SCIENCES, v. 10, p. 1-11, 2022.
33.
BALIZA, ANA ROSA ; ZACARIAS MESQUITA, AMIR ; MORGHI, YOUSSEF . Review of Regulatory Requirements for Implementing an Aging Management System for the IPR-R1 Triga Reactor of CDTN. BRAZILIAN JOURNAL OF RADIATION SCIENCES, v. 10, p. 1-9, 2022.
34.
FELIPPE, A.A.M ; MESQUITA, A. Z. ; LAGE, A.M.F. ; MARQUES, J. G. O. ; Gouveia Silva, W. ; Alcântara e Alves ; ALMEIDA, V. F. . Interfaces visuais para o sistema de simulação digital do reator nuclear TRIGA® IPR-R1 utilizando o programa LabVIEW®. REVISTA TECNOLOGIA, v. 43, p. 1-13, 2022.
35.
MARQUES, R.O. ; VASCONCELOS, V. ; SOARES, W.A. ; SILVA JUNIOR, S. F. ; RASO, A. L. ; MESQUITA, A.Z. . Probabilistic Safety Analysis and Risk-Based Inspection of nuclear research reactors: state-of-the-art and implementation proposal. BRAZILIAN JOURNAL OF RADIATION SCIENCES, v. 8, p. 1-12, 2021.
36.
MORGHI, Y. ; MESQUITA, A.Z. . Numerical Simulation Study on the Air/Water Counter- current Flow Limitation in Nuclear Reactors. BRAZILIAN JOURNAL OF RADIATION SCIENCES, v. 8, p. 1-17, 2021.
37.
Alcântara e Alves ; MESQUITA, A.Z. ; Albernaz Ribeiro. P.M ; OLIVEIRA, A.M. ; PECONICK, D. G. O. ; MORGHI, Y. ; SILVA, E. P. ; RODRIGUES, R.R. . Desenvolvimento de Metodologias e Aplicação de Técnicas de Análise e Gerenciamento de Riscos para Melhorias no Controle, Segurança e Licenciamento de Centrais Nucleares e Instalações Radioativas. Brazilian Applied Science Review (BASR), v. 5, p. 418-428, 2021.
38.
OLIVEIRA, A.M. ; GONCALVES, L. M. ; MESQUITA, A.Z. ; BANDARRA FILHO, E. P. ; FERREIRA, A.G. . Desempenho termo-hidráulico de nanofluidos compostos por nanotubos de carbono de paredes múltiplas funcionalizados (MWCNT-OH/água). RESEARCH, SOCIETY AND DEVELOPMENT, v. 10, p. e5910313031, 2021.
39.
MORGHI, Y. ; MESQUITA, A.Z. ; BALIZA, A.R. . Quality assurance program for Angra 1 licence renewal and long-term operation. BRAZILIAN JOURNAL OF RADIATION SCIENCES, v. 9, p. 1-16, 2021.
40.
MESQUITA, A.Z.; PALMA, D.A.P ; REZENDE, H.C. ; OLIVEIRA, A.M. ; MORGHI, Y. ; RIBEIRO, P. A. M. ; Alcântara e Alves ; PECONICK, D. G. O. . Power Measurement Methodologies for Pool Nuclear Research Reactors. Latin American Journal of Development, v. 3, p. 882-892, 2021.
41.
MATA, J.F.C. ; MESQUITA, A.Z. . The Importance of Probabilistic Safety Assessment in the Careful Study of Risks Envolved to New Nuclear Power Plant Projects. BRAZILIAN JOURNAL OF RADIATION SCIENCES, v. 9, p. 1-20, 2021.
42.
MESQUITA, A.Z.; REZENDE, H.C. ; RODRIGUES, R.R. ; ALMEIDA, V. F. ; PALMA, D.A.P . Experimental evaluation of natural convection in the IPR-R1 Triga research reactor at 264 kW and 105 kW. BRAZILIAN JOURNAL OF RADIATION SCIENCES, v. 9, p. 1-15, 2021.
43.
MESQUITA, A.Z.; REIS, I. C. ; ALMEIDA, V. F. ; RODRIGUES, R.R. . Experimento para Levantamento do Efeito do Boro na Reatividade do Reator Nuclear de Pesquisa Triga IPR-R1. Revista Analytica. NEWSLAB, v. 18, p. 14-20, 2020.
44.
VIANA, W. ; MESQUITA, A.Z. ; ALMEIDA, V. F. ; PALMA, D.A.P . Design of a remote-operated underwater vehicle for visual inspection of research nuclear reactors. ACCENTS Transactions on Image Processing and Computer Vision, v. 5, p. 20-26, 2020.
45.
MORGHI, Y. ; BALIZA, A.R. ; MESQUITA, A.Z. . Commercial grade dedication challenges for Brazilian nuclear industry. BRAZILIAN JOURNAL OF RADIATION SCIENCES, v. 8, p. 1-18, 2020.
46.
OLIVEIRA, A.M. ; MESQUITA, A.Z. ; BANDARRA FILHO, E. P. ; MORALES, D. F. . Thermophysical properties of nanofluids MWCNT (multi-walled carbon nanotubes) in water for emergency coolant from nuclear reactors. BRAZILIAN JOURNAL OF RADIATION SCIENCES, v. 8, p. 2-7, 2020.
47.
MARTINS, E. D. ; MESQUITA, A.Z. ; ALMEIDA, V. F. ; Palma, D. A. P. ; VIANA, W. . Anatomical movement replicator applied to activities in ionizing radiation fields. BRAZILIAN JOURNAL OF RADIATION SCIENCES, v. 8, p. 1-15, 2020.
48.
PALMA, D.A.P ; SOUZA, A. L. B. ; MESQUITA, A.Z. . Funding and Finance Issues Related to the Decommissioning of Brazilian NPPS. BRAZILIAN JOURNAL OF RADIATION SCIENCES, v. 8, p. 1-16, 2020.
49.
MESQUITA, A.Z.; FELIPPE, A.A.M ; LAGE, A.M.F. ; RIBEIRO, P. A. M. . Visual interfaces for the digital simulation system of the IPR-R1 Triga nuclear research reactor. ACCENTS Transactions on Image Processing and Computer Vision (TIPCV), v. 6, p. 80-90, 2020.
50.
FELIPPE, A.A.M ; MESQUITA, A.Z. ; LAGE, A.M.F. ; RODRIGUES, R.R. ; ALVES, V. E. A. E. ; RIBEIRO, P. A. M. ; OLIVEIRA, A.M. . Levantamento das Expressões Numéricas das Variáveis Operacionais do Reator Nuclear Triga do CDTN para sua Simulação Computacional. Brazilian Applied Science Review, v. 4, p. 3545-3555, 2020.
51.
BALIZA, A.R. ; MORGHI, Y. ; MESQUITA, A.Z. . ASME in-service inspection and in-service testing programs for Angra 1. BRAZILIAN JOURNAL OF RADIATION SCIENCES, v. 8, p. 1-19, 2020.
52.
ALMEIDA, V. F. ; RIBEIRO, L. S. ; SILVA, E. F. ; PELUSO, A. F. F. V. ; MEDEIROS, N. S. ; MESQUITA, A.Z. . The current public acceptance in Brazil of nuclear science and technology for peaceful purposes. INTERNATIONAL JOURNAL OF NUCLEAR ENERGY, SCIENCE AND TECHNOLOGY (PRINT), v. 14, p. 328-338, 2020. Citações:1
53.
FELIPPE, A.A.M ; LAGE, A.M.F. ; MESQUITA, A.Z. ; PINTO, A. J. ; RODRIGUES, R.R. ; ALMEIDA, V. F. . ODATriga (Operational Data Acquisition Triga). REVISTA DA PROPRIEDADE INDUSTRIAL, v. 2576, p. 7, 2020.
54.
OLIVEIRA, A.M. ; MESQUITA, A.Z. ; BANDARRA, E. P. ; GOMEZ, A. O. C. ; GONCALVES, L. M. . PROPOSAL FOR AN EXPERIMENTAL STUDY OF THE THERMAL-HYDRAULIC PERFORMANCE OF NANOFLUIDS AS COOLANT IN LIGHT WATER NUCLEAR REACTORS (LWR). DOI: 10.15341/mese(2333-2581)/05.05.2019/013. MODERN ENVIRONMENTAL SCIENCE AND ENGINEERING, v. 5, p. 459-462, 2019.
55.
OLIVEIRA, A.M. ; MESQUITA, A.Z. ; BANDARRA, E. P. ; GOMEZ, A. O. C. ; GONCALVES, L. M. . PROPOSTA DE ESTUDO EXPERIMENTAL DO DESEMPENHO TÉRMICO-HIDRÁULICO DE NANOFLUÍDEOS COMO REFRIGERANTE EM REATORES NUCLEARES DE ÁGUA LEVE (LWR). Revista da Associação Portuguesa de Análise Experimental de Tensões, v. 31, p. 43-47, 2019.
56.
MESQUITA, A.Z.; RODRIGUES, R.R. . SYSTEM TO DETECT LEAKING IN FUEL ELEMENTS IN TRIGA NUCLEAR RESEARCH REACTOR. Revista da Associação Portuguesa de Análise Experimental de Tensões, v. 31, p. 1-9, 2019.
57.
LAGE, A.M.F. ; MESQUITA, A.Z. ; FELIPPE, A.A.M . Design of a digital system for operational parameters simulation of IPR-R1 Triga nuclear research reactor. BRAZILIAN JOURNAL OF RADIATION SCIENCES, v. 7, p. 1-13, 2019.
58.
GUAL, MARITZA R. ; Pereira, Claubia ; Mesquita, Amir Z. . Application of a new source model of a panoramic gamma irradiator on dose map formation in an irradiated product. APPLIED RADIATION AND ISOTOPES, v. 144, p. 87-92, 2019. Citações:8|11
59.
MESQUITA, A.Z.; SALLES, B. M. ; LUCIANO, M. R. . Design of a Visual System to Monitoring Thermal Power in Pool-Type Nuclear Research Reactor. INTERNATIONAL JOURNAL OF ADVANCED ENGINEERING RESEARCH AND SCIENCE, v. 6, p. 243-248, 2019.
60.
MESQUITA, A.Z.; REIS, I. C. ; ALMEIDA, V. F. ; RODRIGUES, R.R. . Boron-10 effect on the reactivity of the IPR-R1 Triga research reactor. ANNALS OF NUCLEAR ENERGY, v. 132, p. 64-69, 2019. Citações:8|6
61.
MESQUITA, A.Z.; LAGE, A.M.F. ; PINTO, A. J. ; STEHLING, E. T. . Software Simula Triga. REVISTA DA PROPRIEDADE INDUSTRIAL, v. 2552, p. 15, 2019.
62.
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, v. 13, p. 24-27, 2018.
63.
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, 2018.
64.
MORGHI, Y. ; MESQUITA, A.Z. ; PUENTE, J. ; BALIZA, A.R. . Investigation of Counter-Current Flow Limitation for Air-Water in a PWR Hot Leg Experimental Loop for Different Geometry. International Journal of Engineering Technology and Management Research, v. 5, p. 198-212, 2018.
65.
SILVA, S. P. A. ; MESQUITA, A.Z. ; REZENDE, H. C. ; Palma, D. A. P. . Thermal-hydraulic code for rewetting analysis in a PWR experimental loop. ANNALS OF NUCLEAR ENERGY, v. 117, p. 290-296, 2018.
66.
GUAL, MARITZA R. ; Mesquita, Amir Z. ; PEREIRA, Cláubia . Evaluation of an alternative shielding materials for F-127 transport package. RADIATION PHYSICS AND CHEMISTRY, v. 144, p. 29-33, 2018. Citações:4|5
67.
RODRIGUES, R.R. ; MESQUITA, A.Z. ; PALMA, D.A.P . Designing a system to detect leaking in fuel elements in Brazilian Triga research reactor. INTERNATIONAL JOURNAL OF NUCLEAR ENERGY, SCIENCE AND TECHNOLOGY (PRINT), v. 12, p. 239, 2018. Citações:1
68.
MORGHI, Y. ; MESQUITA, A.Z. ; ANGULO, J. A. P. ; BALIZA, A.R. . SIMULAÇÃO DO ESCOAMENTO EM CONTRACORRENTE ÁGUA/AR EM REATORES NUCLEARES PWR UTILIZANDO CÓDIGO OPENFOAM. HOLOS (NATAL. ONLINE), v. 6, p. 92-102, 2018.
69.
LAGE, A M.F. ; MESQUITA, A.Z. ; FELIPPE, A.A.M . Digital system project for graphic simulation of operational parameters of the IPR-R1 Triga nuclear research reactor. ACCENTS Transactions on Image Processing and Computer Vision, v. 4, p. 26-32, 2018.
70.
SALLES, B. M. ; MESQUITA, A.Z. ; LUCIANO, M. R. . Development of a research reactor power measurement system using cherenkov radiation. ACCENTS Transactions on Image Processing and Computer Vision, v. 4, p. 33-38, 2018.
71.
HENRICE JR, E. ; PALMA, D.A.P ; GONÇALVES, A.C. ; MESQUITA, A.Z. . Support to the identification of anomalies in an external neutron source using Hurst Exponents. PROGRESS IN NUCLEAR ENERGY, v. 99, p. 119-126, 2017. Citações:5|7
72.
GUAL, M. R. ; MESQUITA, A.Z. ; Ribeiro, E. ; Grossi, P.A. . Shielding Verifications for a Gamma Irradiation Facility Considering the Installation of a New Automatic Product Loading System. Science and Technology of Nuclear Installations, v. 2017, p. 1-6, 2017. Citações:5|6
73.
MEIRELES, S. P. ; MESQUITA, A.Z. ; PALMA, D.A.P ; ANTOLIN, M. Q. ; CAMPOLINA, D.A.M. ; MENEZES, M.A.B.C. . Influence of geometry in TRIGA reactor criticality calculation and reactivity determination using Serpent 2 and MCNPX codes. INTERNATIONAL JOURNAL OF NUCLEAR ENERGY, SCIENCE AND TECHNOLOGY (PRINT), v. 11, p. 146-162, 2017.
74.
MESQUITA, A.Z.; MOREIRA, R. M. . Disciplina: História da Ciência - Tecnologia Nuclear, contribuição para a formação dos estudantes de pós-graduação em Engenharia. RBPG. REVISTA BRASILEIRA DE PÓS-GRADUAÇÃO, v. 14, p. 1-16, 2017.
75.
GUAL, M. R. ; MILIAN, F.M. ; MESQUITA, A.Z. ; PEREIRA, C. . New Source Models to Represent the Irradiation Process in Panoramic Gamma Irradiator. APPLIED RADIATION AND ISOTOPES, v. 128, p. 11-21, 2017. Citações:5|7
76.
MEIRELES, S. P. ; MESQUITA, A.Z. ; MENEZES, M. A. B. ; GUAL, M. R. ; PALMA, D.A.P . Simulação neutrônica do reator nuclear de pesquisa TRIGA, do CDTN, utilizando os códigos Monte Carlo Serpent e MCNPX. Revista Tecnologia, v. 38, p. 3-12, 2017.
77.
RODRIGUES, R.R. ; MESQUITA, A.Z. . Desenvolvimento de sistema para inspeção de elementos combustíveis de reatores nucleares de pesquisa Triga. Revista Tecnologia, v. 38, p. 3-13, 2017.
78.
MATA, JÔNATAS FRANCO CAMPOS DA MATA ; MESQUITA MESQUITA, AMIR ZACARIAS . Utilização da análise probabilística de segurança como metodologia de avaliação e gerenciamento de riscos inerentes a usinas nucleoelétricas / Use of Probabilistic Safety Assessment as methodology for the evaluation and management of risks inherent in nuclear power plants. Revista Internacional de Tecnología, Ciencia y Sociedad, v. 6, p. 62-66, 2017.
79.
MESQUITA, A. Z.; PINTO, A. J. ; LAGE, A.M.F. ; MARTINS, E. D. ; SOUZA, W.F. . Simulação da partida de reator nuclear de pesquisa utilizando instrumentos virtual instruments. REVISTA TECNOLOGIA, v. 38, p. 13-21, 2017.
80.
SALLES, S. ; MESQUITA, A.Z. . As fontes de geração de energia conhecidas atualmente não conseguirão atender a futura demanda mundial. REVISTA INTERNACIONAL DE CIENCIA Y SOCIEDAD, v. 3, p. 15-25, 2016.
81.
PALMA, D.A.P ; GONÇALVES, A.C. ; MESQUITA, A.Z. ; MARTINEZ, A. S. . A new formulation for the Doppler broadening function relaxing the approximations of Beth-Plackzec. Annals of Nuclear Energy, v. 88, p. 68-72, 2016. Citações:2|4
82.
MESQUITA, A.Z.; LADEIRA, L. C. D. ; PALMA, D.A.P . An Innovative Method for Online Power Monitoring in Nuclear Reactors. RECENT PATENTS ON SIGNAL PROCESSING, v. 5, p. 61-67, 2016.
83.
MESQUITA, A.Z.; LAMEIRAS, F.S. ; MARTINS, M. D. . O ensino de tecnologia de reatores nucleares em um programa de pós-graduação de Engenharia Multidisciplinar. RBPG. Revista Brasileira de Pós-Graduação, v. 12, p. 839-855, 2016.
84.
MESQUITA, A.Z.; LADEIRA, L. C. D. ; Palma, D. A. P. ; GUAL, M. R. . Uncertainty assessment of the experimental thermal-hydraulic parameters for CDTN TRIGA research reactor. International Journal of Nuclear Energy, Science and Technology (Print), v. 10, p. 201-2016, 2016. Citações:3
85.
GUAL, M. R. ; MESQUITA, A.Z. ; CAMPOLINA, D.A.M. ; RODRIGUES, R.R. . Dosimetry assessment during the sipping test in the IPR-R1 TRIGA reactor using MCNPX. PROGRESS IN NUCLEAR ENERGY, v. 93, p. 238-245, 2016. Citações:4|6
86.
Mesquita, Amir Zacarias; LAGE, ALDO MÁRCIO FONSECA ; MARTINS, ELDRICK D. ; GUAL, MARITZA RODRÍGUEZ ; PALMA, DANIEL ARTUR PINHEIRO . A human-machine interface for a TRIGA research reactor of Brazil. INTERNATIONAL JOURNAL OF NUCLEAR ENERGY, SCIENCE AND TECHNOLOGY (PRINT), v. 10, p. 369-379, 2016.
87.
LADEIRA, L. C. D. ; MESQUITA, A.Z. ; PEREIRA, M.T. ; RESENDE, C.C.M. . Experimental determination of dose uniformity in the CDTN gamma irradiator. International Journal of Nuclear Energy, Science and Technology (Print), v. 9, p. 42-55, 2015. Citações:3
88.
MATA, J.F.C. ; MESQUITA, A.Z. ; VASCONCELOS, V. . Estudos científicos para controle, segurança e licenciamento de centrais nucleares. DOI: 10.18848/2474-6010/CGP/v02i01/99-107. REVISTA INTERNACIONAL DE CIENCIA Y SOCIEDAD, v. 2, p. 98-107, 2015.
89.
Reis, P.A.L. ; Costa, A.L. ; PEREIRA, C. ; VELOSO, M. A. F. ; MESQUITA, A.Z. . Simulation of a TRIGA Reactor Core Blockage Using RELAP5 Code. Science and Technology of Nuclear Installations, v. 2015, p. 1-10, 2015. Citações:5|5
90.
LADEIRA, L. C. D. ; MESQUITA, A.Z. ; PEREIRA, M.T. . Calibrations of Amber Perspex-PMMA Dosimeter in the CDTN Gamma Irradiator Operational Conditions. Journal of Energy and Power Engineering, v. 9, p. 245-251, 2015.
91.
LADEIRA, L. C. D. ; MESQUITA, A.Z. ; PEREIRA, M.T. . Determination of absorbed dose in CDTN gamma irradiator using Fricke dosimeters. International Journal of Nuclear Energy, Science and Technology (Print), v. 9, p. 105, 2015.
92.
Palma, D. A. P. ; MESQUITA, A.Z. ; MARTINEZ, A. S. ; GONÇALVES, A.C. . Assessment of thermo-mechanical performance of fuel elements with the use of CNFR and FRAPCON codes. International Journal of Nuclear Energy, Science and Technology (Print), v. 9, p. 116, 2015. Citações:1
93.
LADEIRA, L. C. D. ; MESQUITA, A.Z. ; PEREIRA, M.T. . Calibrations of Red Perspex PMMA dosimeter in terms of absorbed dose to water for routine dosimetry at CDTN gamma irradiation laboratory. International Journal of Nuclear Energy, Science and Technology (Print), v. 9, p. 238, 2015.
94.
Henrice, E.Jr. ; PALMA, D.A.P ; MARTINEZ, A. S. ; MESQUITA, A.Z. . Neutronic flux analysis in subcritical systems using the R/S and DFA methods. Transactions of the American Nuclear Society, v. 113, p. 1317-1320, 2015.
95.
MESQUITA, A.Z.. Power monitoring in nuclear reactors. JOURNAL OF ELECTRICAL ENGINEERING AND ELECTRONIC TECHNOLOGY, v. 4, p. 15, 2015.
96.
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, 2014. Citações:1
97.
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, v. 8, p. 145-153, 2014.
98.
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, 2014.
99.
MESQUITA, A.Z.; SOUZA, R. M. G. P. . Thermal-hydraulic and neutronic experimental research in the TRIGA reactor of Brazil. PROGRESS IN NUCLEAR ENERGY, v. 76, p. 183-190, 2014. Citações:3|7
100.
MESQUITA, A.Z.; PALMA, D.A.P ; SALLES, S. . Coolant Monitoring of the CDTN TRIGA Nuclear Research Reactor. International Journal of Mechanical Engineering and Automation, v. 1, p. 111-117, 2014.
101.
MESQUITA, A.Z.. Processo para Monitoramento em Tempo Real da Potência de Reatores Nucleares pela Medida da Temperatura do Combustível e do Refrigerante. Revista da Propriedade Industrial, v. 1, p. 58-58, 2014.
102.
Palma, D. A. P. ; GONÇALVES, A.C. ; MARTINEZ, A. S. ; MESQUITA, A.Z. . The Influence in Disregarding the First Approximation of Bethe-Plackzec in the Calculation of Resonance Self-Shielding Factors. Transactions of the American Nuclear Society, v. 111, p. 716-719, 2014. Citações:1
103.
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, 2013.
104.
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, 2013.
105.
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. DOI: 10.11648/j.ijepe.20130202.16.. INTERNATIONAL JOURNAL OF ENERGY AND POWER ENGINEERING, v. 2, p. 69-76, 2013.
106.
MESQUITA, A.Z.; SILVA, V.V.A ; 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, 2013.
107.
PALMA, D.A.P ; MESQUITA, A.Z. . IN-PILE EXPERIMENTS IN A URANIUM-ZIRCONIUM-HYDRIDE TRIGA FUEL (IAEA-TECDOC-CD series no. 1726). in-pile Testing and Instrumentation for Development of Generation-IV Fuels and Materials, v. 1, p. 171-182, 2013.
108.
Reis, Patrícia A.L. ; Costa, Antonella L. ; Pereira, Claubia ; Silva, Clarysson A.M. ; Veloso, Maria Auxiliadora F. ; MESQUITA, A.Z. . Sensitivity analysis to a RELAP5 nodalization developed for a typical TRIGA research reactor. Nuclear Engineering and Design (Print), v. 242, p. 300-306, 2012. Citações:8|8
109.
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, 2012.
110.
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. Citações:1
111.
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. 101-114, 2012.
112.
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.
113.
MESQUITA, A.Z.; Costa, A.L. ; PEREIRA, C. ; Veloso, M.A.. ; Reis, P.A.L. . Experimental investigation of the onset of subcooled nucleate boiling in an open-pool nuclear research reactor. ASTM Special Technical Publication, v. 1534, p. 183-197, 2012. Citações:3
114.
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 (Print), v. 6, p. 153-165, 2011. Citações:3
115.
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 (Online), v. 8, p. 51-60, 2011.
116.
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. Científica, v. 15, p. 17-24, 2011.
117.
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 (New Series), v. 53, p. 1126-1131, 2011. Citações:7|9
118.
SOUZA, R. M. G. P. ; MESQUITA, A.Z. . REACTIVITY BALANCE IN THE IPR-R1 TRIGA REACTOR. Progress in Nuclear Energy (New Series), v. 53, p. 1132-1135, 2011. Citações:6|8
119.
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 (New Series), v. 53, p. 1197-1203, 2011. Citações:11|16
120.
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, 2011.
121.
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. Citações:7|14
122.
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, 2010. Citações:2|4
123.
Lombardi Costa, A. ; 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, 2010. Citações:23|24
124.
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, v. 14, p. 55-60, 2010.
125.
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, 2010. Citações:27|30
126.
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, p. 51-62, 2010.
127.
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, p. 41-50, 2010.
128.
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, p. 03-12, 2010.
129.
Grossi, P.A. ; Tello, C.C.O. ; MESQUITA, A.Z. . IPR-R1 TRIGA RESEARCH REACTOR DECOMMISSIONING (STI/PUB/1460). International Atomic Energy Agency. Proceedings Series, v. 1, p. 274-284, 2010.
130.
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, 2008.
131.
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, 2007. Citações:1
132.
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, 2007. Citações:2
133.
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 (Impresso), v. XXIX, p. 240-245, 2007. Citações:10|17
134.
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, Madrid, v. 9, n.1, p. 37-45, 2005.
135.
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. Revista Brasileira de Pesquisa e Desenvolvimento - Research and Development Brazilian Journal, Vol. 4 - no. 2, Setembro 2002.. Revista Brasileira de Pesquisa e Desenvolvimento, Rio de Janeiro, v. 4, p. 285-290, 2002.
136.
MESQUITA, A.Z.; LADEIRA, L. C. D. . Dispositivo para Desencapar Termopares de Isolação Mineral, pela Remoção de sua Blindagem por Corrente Elétrica. Revista da Propriedade Industrial, v. 1, p. 15-15, 1987.
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Capítulos de livros publicados
1.
Alfenas, Ricardo Augusto da Silva ; Mesquita, Amir Zacarias ; PALMA, DANIEL ARTUR PINHEIRO ; SILVA, ELLEN DE OLIVEIRA . AVALIAÇÃO SEMIQUANTITATIVA DA PERDA DE CONHECIMENTO POR INDIVÍDUO NO ÓRGÃO REGULADOR NUCLEAR BRASILEIRO. AVALIAÇÃO SEMIQUANTITATIVA DA PERDA DE CONHECIMENTO POR INDIVÍDUO NO ÓRGÃO REGULADOR NUCLEAR BRASILEIRO. 1ed.Piracanjuba-GO: Editora Conhecimento Livre, 2025, v. 1, p. 15-36.
2.
MESQUITA, A. Z.; Palma, D. A. P. ; SOUSA, A. L. B. ; SILVA, E. O. . UMA IMPRESSÃO ACERCA DO PROGRAMA NUCLEAR BRASILEIRO SEGUNDO O IAEA SERVICES SERIES NG-G-3.1: AVALIAÇÃO DA PERDA DE CONHECIMENTO INDIVIDUAL NO ÓRGÃO REGULADOR BRASILEIRO. In: Eduardo Ferreira Molina. (Org.). Exact Sciences and their Advances. 1ed.Curitba: Editora Reflexão Acadêmica, 2023, v. 1, p. 117-127.
3.
Alcântara e Alves ; MESQUITA, A.Z. ; BALIZA, A.R. ; OLIVEIRA, A.M. ; PECONICK, D. G. O. ; MORGHI, Y. ; SILVA, E. P. ; Albernaz Ribeiro. P.M . GERENCIAMENTO DE RISCOS PARA MELHORIAS NO CONTROLE, SEGURANÇA E LICENCIAMENTO DE CENTRAIS NUCLEARES E INSTALAÇÕES RADIATIVAS: APLICAÇÃO DE TÉCNICAS DE ANÁLISE. In: Edilson Antonio Catapan. (Org.). Avanços dos estudos científicos na área das ciências exatas. 1ed.São José dos Pinhais/PR: Brazilian Journals Publicações de Periódicos e Editora Ltda., 2022, v. 1, p. 269-280.
4.
FELIPPE, A.A.M ; MESQUITA, A.Z. ; LAGE, A M.F. . LEVANTAMENTO DAS EXPRESSÕES NUMÉRICAS DAS VARIÁVEIS OPERACIONAIS DO REATOR NUCLEAR TRIGA DO CDTN PARA DESENVOLVIMENTO DO SIMULADOR DIGITAL DE SUA OPERAÇÃO. In: Barbara Luzia Sartor Bonfim Catapan. (Org.). Contribuições para o avanço da ciência e tecnologia. 1ed.Curitiba: Editora Reflexão Acadêmica, 2022, v. 01, p. 162-170.
5.
OLIVEIRA, A.M. ; MESQUITA, A.Z. ; REIS, I. C. . PROPOSTA DE INVESTIGAÇÃO EXPERIMENTAL DO DESEMPENHO TERMO-HIDRAULICO DE NANOFLUIDOS NA REFRIGERAÇÃO DE REATORES NUCLEARES À ÁGUA LEVE. In: Antonella Carvalho de Oliveira. (Org.). Projeto, Análise e Otimização na Área das Engenharias. 1ed.Ponta Grossa (PR): Atena Editora, 2021, v. 1, p. 124-130.
6.
Mata, Jônatas Franco Campos da ; Mesquita, Amir Zacarias ; Mendes, Bárbara Luísa Nunes Pereira ; Vales, Bianca dos Santos ; Souza, Eliane Alves ; Azevedo, Emanuel Henrique Alves ; Sobrinho, Enis de Campos Maciel ; Vieira, Ianca Alberta Caires ; Alcântara, Jackson Ramon Silva ; Vilane, Luiza Souza ; Soares, Matheus Jesus ; Nascimento, Pedro Henrique Gomes do ; Lopes, Thalles Rômulo Silva . ANÁLISE COMPARATIVA DA UTILIZAÇÃO DE ANÁLISE PROBABILÍSTICA DE SEGURANÇA NO LICENCIAMENTO DE CENTRAIS NUCLEARES EM ÂMBITO NACIONAL E MUNDIAL. In: Dallamuta, J.; Holzmann, H.A.; Kanashiro, R.O.. (Org.). Engenharias: Metodologias e Práticas de Caráter Multidisciplinar 3. 1ed.Ponta Grossa: Atena Editora, 2021, v. 3, p. 11-19.
7.
Cesar, Hugo ; dos Santos, Andre Augusto Campagnole ; Alberto, Moyses ; Zacarias, Amir ; Jordao, Elizabete . Experimental Investigation and Computational Validation of Thermal Stratification in Piping Systems of PWR Reactors. In: Amir Z. Mesquita, Ms Mirna Cvijic. (Org.). Book: Current Research in Nuclear Reactor Technology in Brazil and Worldwide. 1ed.Rijeka: InTech - Open Access Publisher, 2013, v. 1, p. 3-27.
8.
P. Palma, Daniel Artur ; C. Goncalves, Alessandro da ; Senra, Aquilino ; Zacarias, Amir . New Methods in Doppler Broadening Function Calculation. In: Amir Z. Mesquita; Ms Mirna Cvijic. (Org.). Book: Current Research in Nuclear Reactor Technology in Brazil and Worldwide. 1ed.Rijeka: InTech - Open Access Publisher, 2013, v. 1, p. 29-53.
9.
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, 2013, v. 1, p. 69-70.
10.
Zacarias, Amir; P. Palma, Daniel Artur ; Lombardi, Antonella ; Pereira, Clubia ; F. Veloso, Maria Auxiliadora ; L. Reis, Patrcia Amlia . Experimental Investigation of Thermal Hydraulics in the IPR-R1 TRIGA Nuclear Reactor. In: Amir Z. Mesquita; Iva Simcic. (Org.). Nuclear Reactors. 1ed.: , 2012, v. 1, p. 1-24.
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MESQUITA, A.Z.; PINTO, A. J. ; Tello, C.C.O. ; LAMEIRAS, F.S. . Chapter 4 - Digital Control System Simulation for Nuclear Reactor Neutronic Parameters. In: Morena J. Acosta. (Org.). Book: Advances in Energy Research. Volume 10. 1ed.Hauppauge, NY/USA: Nova Science Publishers, Inc., 2012, v. 10, p. 56-70.
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Mesquita, Amir Z.; Costa, Antonella L. ; PEREIRA, C. ; Veloso, Maria A. F. ; REIS, P. A. L. . Experimental Investigation of the Onset of Subcooled Nucleate Boiling in an Open-Pool Nuclear Research Reactor. In: Prabhu, K.N.; Kobasko, N.. (Org.). Film and Nucleate Boiling Processes. 1ed.West Conshohocken: ASTM International, 2012, v. 1, p. 183-197.
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L., Antonella ; L. Reis, Patricia A. ; M. Silva, Clarysson A. ; Pereira, Claubia ; F. Veloso, Maria Auxiliadora ; T., Bruno ; V., Humberto ; Z., Amir . Safety Studies and General Simulations of Research Reactors Using Nuclear Codes. In: Dr. Pavel V. Tsvetkov; Petra Zobic. (Org.). Book: Nuclear Power - System Simulations and Operation. 1ed.Rijeka/Croatia: InTech - Open Access Publisher, 2011, v. 2, p. 21-42.
