Amir Mesquita

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

The aim of this book is to disseminate state-of-the-art research and advances in the area of nuclear reactors technology. The book was divided in two parts.Topics discussed in the first part of this compilation include: experimental investigation and computational validation of thermal stratification in PWR reactors piping systems, new methods in doppler broadening function calculation for nuclear reactors fuel temperature, isothermal phase transformation of uranium-zirconium-niobium alloys for advanced nuclear fuel, reactivity Monte Carlo burnup simulations of enriched gadolinium burnable poison for PWR fuel, utilization of thermal analysis technique for study of uranium-molybdenum fuel alloy, probabilistic safety assessment applied to research reactors, and a review on the state-of-the art and current trends of next generation reactors. The second part includes: thermal hydraulics study for a ultra high temperature reactor with packed sphere fuels, benefits in using lead-208 coolant for fast reactors and accelerator driven systems, nuclear power as a basis for future electricity production in the world: Generation III and IV reactors, nanostructural materials and shaped solids for improvement and energetic effectiveness of nuclear reactors safety and radioactive wastes, multilateral nuclear approach to nuclear fuel cycles, and a cold analysis of the Fukushima accident.

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