Neutronic evaluation of CANDU-6 core using reprocessed fuels.

Autores

  • Clarysson Alberto Mello da Silva Universidade Federal de Minas Gerais image/svg+xml
  • Carlos Eduardo Velasquez Cabrera Universidade Federal de Minas Gerais image/svg+xml
  • Michel Cleberson Bernardo de Almeida Universidade Federal de Minas Gerais image/svg+xml
  • Rochkhudon Batista de Faria Universidade Federal de Minas Gerais image/svg+xml
  • Claubia Pereira Universidade Federal de Minas Gerais image/svg+xml

DOI:

https://doi.org/10.15392/bjrs.v8i3.1219

Palavras-chave:

CANDU reactor, DUPIC cycle, AIROX, OREOX, MCNPX 2.6.0

Resumo

  

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Biografia do Autor

  • Clarysson Alberto Mello da Silva, Universidade Federal de Minas Gerais
      
  • Carlos Eduardo Velasquez Cabrera, Universidade Federal de Minas Gerais
      
  • Michel Cleberson Bernardo de Almeida, Universidade Federal de Minas Gerais
      
  • Rochkhudon Batista de Faria, Universidade Federal de Minas Gerais
      
  • Claubia Pereira, Universidade Federal de Minas Gerais
      

Referências

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27-09-2020

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Neutronic evaluation of CANDU-6 core using reprocessed fuels. Brazilian Journal of Radiation Sciences, Rio de Janeiro, Brazil, v. 8, n. 3, 2020. DOI: 10.15392/bjrs.v8i3.1219. Disponível em: https://bjrs.org.br/revista/index.php/REVISTA/article/view/1219. Acesso em: 17 jul. 2025.