Neutronic study of ELECTRA using reprocessed fuel and depleted uranium

Clarysson Alberto Mello da silva; Paola Machado de Almeida; Claubia Claubia Pereira

doi:10.15392/2319-0612.2024.2677

Autores/as

Clarysson Alberto Mello da silva Universidade Federal de Minas Gerais http://orcid.org/0000-0002-3082-644X (no autenticado)
Paola Machado de Almeida Universidade Federal de Minas Gerais
Claubia Claubia Pereira Universidade Federal de Minas Gerais

DOI:

https://doi.org/10.15392/2319-0612.2024.2677

Palabras clave:

Small Modular Reactors, Lead Cooled Reactor, ELECTRA, MCNP6.2.0

Resumen

The present work simulates the European Lead Cooled Training Reactor (ELECTRA), focusing on studying the neutronic parameters of a small fast nuclear reactor. The goal is to evaluate the possibility of incinerating minor actinides and the potential for energy production from ²³⁸U. The simulations consider the following scenarios: depleted uranium mixed with the reprocessed fuel, and individual fuel rods containing only depleted uranium positioned at different locations within the reactor core. The results show that the use of reprocessed fuels could contribute to the reduction of minor actinides, while the use of depleted uranium reduces reactor criticality by acting as a neutron absorber. Most uranium nuclides do not undergo fission during burnup, which increases their isotopic concentration.

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Biografía del autor/a

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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