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The discrete ordinate method for angular flux calculations in slab geometry.

M Lahdour1, T El Bardouni1, M Mohammed1

  • 1Radiations and Nuclear Systems Laboratory, University Abdelmalek Essaadi, Faculty of Sciences of Tetuan, Morocco.

Heliyon
|August 21, 2019
PubMed
Summary

This study presents a new matrix form for the discrete ordinate (S) method to accurately calculate neutron angular flux in reactor cores. Results demonstrate its effectiveness compared to MCNP6 simulations.

Keywords:
Angular fluxMCNP6Neutron transport equationNuclear physics

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Area of Science:

  • Nuclear Engineering
  • Computational Physics

Background:

  • Deterministic methods for neutron transport require better angular flux representation for reactor core analysis.
  • Accurate neutron population data is crucial for reactor design and safety.

Purpose of the Study:

  • To provide a reference-quality calculation for neutron angular flux.
  • To develop and validate a new matrix form for the discrete ordinate method.

Main Methods:

  • The discrete ordinate (S) method was employed using a novel matrix formulation.
  • The model simulates isotropic and anisotropic multiplicative systems in multi-region Cartesian geometry for a single energy group.

Main Results:

  • The new matrix form of the S method was successfully implemented.
  • Calculated angular flux results were compared against the MCNP6 code.

Conclusions:

  • The developed matrix form offers a practical approach for global angular flux representation.
  • The method shows promise for accurate neutron population analysis in nuclear reactors.