Simulação Neutrônica do Núcleo de um Reator Nuclear do Tipo iPWR Usando o Código SERPENT

Mariana Cecilia Betancourt; Leorlen Rojas Mazaira; Carlos Rafael García Hernández; Dany Dominguez; Carlos Alberto Brayner de Oliveira Lira

doi:10.14295/vetor.v31i1.13575

Authors

Mariana Cecilia Betancourt
Leorlen Rojas Mazaira https://orcid.org/0000-0002-9051-7032
Carlos Rafael García Hernández https://orcid.org/0000-0001-8335-7790
Dany Dominguez Universidade Estadual de Santa Cruz - UESC https://orcid.org/0000-0002-0640-2970
Carlos Alberto Brayner de Oliveira Lira https://orcid.org/0000-0002-8287-4822

DOI:

https://doi.org/10.14295/vetor.v31i1.13575

Keywords:

computational neutronic, extended fuel cycle, iPWR reactor, Serpent code

Abstract

Nuclear energy is one of the main alternatives for future energy sources without greenhouse gas emissions. Small modular nuclear reactors have great potential for future development. And among them, due to their safety characteristics and similarity to current reactors, the integral pressurized water reactors (iPWR) stand out. In the work, a neutronic computational model based on the Monte Carlo Serpent code is presented for the design of a four-year extended fuel cycle. The main results of the core neutronic behavior for the extended fuel cycle are offered.

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