Simulation of the burnup in cell calculation using the wimsd-5b code considering different nuclear data libraries

Authors

  • Desirée Yael de Sena Tavares INSTITUTO DE ENGENHARIA NUCLEAR
  • Adilson Costa da Silva INSTITUTO DE ENGENHARIA NUCLEAR
  • Zelmo Rodrigues de Lima INSTITUTO DE ENGENHARIA NUCLEAR

DOI:

https://doi.org/10.15392/bjrs.v9i2A.404

Keywords:

cell or network calculation, WIMSD5B, burnup

Abstract

This work proposes to implement the cell calculation considering the fuel burning using the WIMSD-5B code. The cell calculation procedure allows determining the nuclear parameters present in the multi-group neutron diffusion equation and for this purpose the neutron transport theory is used in a problem with dimensional reduction, but in contrast is considered a large number of groups associated with the neutron spectrum. There are a variety of reactor physics codes that determine the nuclear parameters by solving the neutron transport equation applied to an equivalent cell representing a fuel element. The WIMSD-5B code is a deterministic code that solves the transport equation using collision probability method. The simulation of fuel burning in the cell calculation took into account different nuclear data libraries. The WIMSD-5B code supports several nuclear data libraries and in the present work the following libraries were used: IAEA, ENDFB-VII.1, JENDL3.2, JEFF3.1 and JEF2.2, all formatted for 69 energy groups.

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Published

2021-07-24

Issue

Section

XX Meeting on Nuclear Reactor Physics and Thermal Hydraulics (XX ENFIR)

How to Cite

Simulation of the burnup in cell calculation using the wimsd-5b code considering different nuclear data libraries. Brazilian Journal of Radiation Sciences, Rio de Janeiro, Brazil, v. 9, n. 2A (Suppl.), 2021. DOI: 10.15392/bjrs.v9i2A.404. Disponível em: https://bjrs.org.br/revista/index.php/REVISTA/article/view/404. Acesso em: 23 dec. 2024.

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