Development of Monte Carlo Models for Neutronic Simulation of SEALER

Jefferson Quintão Campos Duarte; Thalles Oliveira Campagnani; Claubia Pereira; Clarysson Alberto Mello da Silva

doi:10.15392/2319-0612.2024.2678

Authors

J. Q. C. Duarte Universidade Federal de Minas Gerais
T. O. Campagnani Universidade Federal de Minas Gerais
C. Pereira Universidade Federal de Minas Gerais
Clarysson Alberto Mello da Silva Universidade Federal de Minas Gerais https://orcid.org/0000-0002-3082-644X

DOI:

https://doi.org/10.15392/2319-0612.2024.2678

Keywords:

Small Modular Reactors, Lead-cooled Fast Reactor, SEALER-Arctic , Neutronic Simulations, MCNP 6.2.0, OpenMC 0.14.0

Abstract

This work focuses on modeling the Swedish Advanced Lead Reactor (SEALER-Artic), considering current trends in the development of Small Modular Reactors (SMRs) and the well-known advantages of lead-cooled nuclear systems. The objective of the study is to compare neutronic parameters using the following stochastic codes: Monte Carlo N-Particle, version 6.2.0 (MCNP 6.2.0), and Open Monte Carlo, version 0.14.0 (OpenMC 0.14.0). In this context, the neutron energy spectrum, the radial neutron flux profile in the reactor core, the relative power distribution, the criticality, and the fuel evolution during the burnup cycle of SEALER-Artic are evaluated. The steady-state results show good agreement of neutronic parameters between the codes. After the burnup, the final fuel composition shows a greater difference, possibly due to the nuclear data used in the decay calculation and the truncation of the atomic fraction calculation during the fuel evolution simulation.

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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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