Fuel assessment for Argonauta using MCNPX

Autores

  • Victor Lusis Lassance Cunha Instituto de Engenharia Nuclear - IEN/CNEN
  • Francisco José de Oliveira Ferreira Instituto de Engenharia Nuclear/CNEN

Palavras-chave:

research reactor, MCNPX, computational simulation

Resumo

As a response to new demands for the Argonauta research reactor, a new fuel load is necessary in order to increase the neutron flux. This report shows a series of tests made in MCNPX in order to assess which fuel will be best suited for Argonauta's future applications.

Biografia do Autor

Victor Lusis Lassance Cunha, Instituto de Engenharia Nuclear - IEN/CNEN

Físico (UFF) e Mestre em Engenharia Nuclear (IME) com enfoque em simulação computacional para Física de Reatores

Referências

X-5 MONTE CARLO TEAM. MCNP. A General Monte Carlo N-Particle Transport Code. Version 5. v. 1/2/3, Los Alamos: LANL, 2003.

LEWIS, E. E. Fundamentals of nuclear reactor physics. 1. ed. Amsterdam: Academic Press, 2008. 280 p.

Capa Progress Report 2015-2017

Downloads

Publicado

2021-07-08

Como Citar

Lassance Cunha, V. L., & Ferreira, F. J. de O. (2021). Fuel assessment for Argonauta using MCNPX. Instituto De Engenharia Nuclear: Progress Report, (3), 114. Recuperado de https://revistas.ien.gov.br/index.php/ienprogressreport/article/view/362

Edição

n. 3 (2018): IEN - Progress Report 2015-2017 n.3

Seção

Engineering and Reactor Safety

Licença

Copyright (c) 2018 Victor Lusis Lassance Cunha, Francisco José de Oliveira Ferreira

Creative Commons License

Este trabalho está licenciado sob uma licença Creative Commons Attribution-NonCommercial-NoDerivatives 4.0 International License.