Amir Mesquita

Titular Researcher III and ProfessorNuclear Technology Development Center (CDTN) / Brazilian Nuclear Energy Commission (CNEN)

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). He is Scholarship of Productivity and Technological Development of Innovative Extension at Brazilian Council for Scientific and Technological Development (CNPq). He is Professor and Collegiate Board Member of the PostGraduate Program in Science and 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 editor: Nuclear Reactors of the InTech Publisher (Croatia). Editorial Board Member of the journals: 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, Intech Open Access Publisher, and Journal on Nuclear Energy Management and Safety (UK).

2books edited

4chapters authored

Latest work with IntechOpen by Amir Mesquita

This book presents a comprehensive review of studies in nuclear reactors technology from authors across the globe. Topics discussed in this compilation include: thermal hydraulic investigation of TRIGA type research reactor, materials testing reactor and high temperature gas-cooled reactor; the use of radiogenic lead recovered from ores as a coolant for fast reactors; decay heat in reactors and spent-fuel pools; present status of two-phase flow studies in reactor components; thermal aspects of conventional and alternative fuels in supercritical water?cooled reactor; two-phase flow coolant behavior in boiling water reactors under earthquake condition; simulation of nuclear reactors core; fuel life control in light-water reactors; methods for monitoring and controlling power in nuclear reactors; structural materials modeling for the next generation of nuclear reactors; application of the results of finite group theory in reactor physics; and the usability of vermiculite as a shield for nuclear reactor.

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