Fuel assessment for Argonauta using MCNPX

Authors

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

Keywords:

research reactor, MCNPX, computational simulation

Abstract

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.

Author Biography

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

Serviço de Tecnologia e Engenharia de Reatores, Física de reatores

References

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

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Published

2021-07-08

How to Cite

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

Issue

No. 3 (2018): IEN - Progress Report 2015-2017 n.3

Section

Engineering and Reactor Safety

License

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

Creative Commons License

This work is licensed under a Creative Commons Attribution-NonCommercial-NoDerivatives 4.0 International License.