Overview of Fourth Generation Reactors Studied at the Universidade Federal de Minas Gerais (Brazil)

Clarysson Alberto Mello da Silva; Anderson Altair Pinheiro de Macedo; Maurício Gilberti; Fabiano Cardoso da Silva; Isabella Resende Magalhães; Antonella Lombardi Costa; Claubia Pereira

doi:10.15392/2319-0612.2024.2419

Authors

Clarysson Alberto Mello da Silva Universidade Federal de Minas Gerais https://orcid.org/0000-0002-3082-644X
Anderson Altair Pinheiro de Macedo Universidade Federal de Minas Gerais
Maurício Gilberti Universidade Federal de Minas Gerais
Fabiano Cardoso da Silva Universidade Federal de Minas Gerais
Isabella Resende Magalhães Universidade Federal de Minas Gerais
Antonella Lombardi Costa Universidade Federal de Minas Gerais
Claubia Pereira Universidade Federal de Minas Gerais

DOI:

https://doi.org/10.15392/2319-0612.2024.2419

Keywords:

Generation Four Nuclear Reactors, Nuclear Fuel Cycle, Neutronic simulations

Abstract

This paper presents the results of the studies about the Fourth Generation Reactors developed at DENU-UFMG, such as the Very High Temperature Reactor (VHTR), Molten Salt Breeder Reactor (MSBR), Sodium Fast Reactor (SFR) and Gas-cooled Fast Reactor (GFR). These studies evaluate neutronic parameters of the nuclear system at steady state and during the burnup using computer models developed at DENU-UFMG using SCALE 6.0 (KENO-VI/ORIGENS), MCNPX 2.6.0 and MCNP5. The results show that the adopted methodologies confirm the capabilities of the codes to simulate specific situations in steady state or transient operating conditions.

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Author Biography

Clarysson Alberto Mello da Silva, Universidade Federal de Minas Gerais

Professor Adjunto da Universidade Federal de Minas Gerais (UFMG) onde desenvolve atividades de ensino e de pesquisa no Departamento de Engenharia Nuclear (DENU). Possui Doutorado (2009) e Mestrado (2005) em Ciências e Técnicas Nucleares pela UFMG, Especialização em Ensino de Física - Universidade Federal de Ouro Preto (UFOP, 2000) e Graduação em Matemática (Licenciatura Plena) - Faculdades Integradas Newton Paiva (FINP, 1996). Possui experiência na área de Engenharia Nuclear com ênfase em Tecnologia Nuclear, atuando em temas relacionados a simulação de sistemas nucleares, reatores avançados, ciclo do combustível, transmutação nuclear e reprocessamento do combustível queimado.

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