Heliyon (Aug 2019)

The discrete ordinate method for angular flux calculations in slab geometry

  • M. Lahdour,
  • T. El Bardouni,
  • M. Mohammed,
  • S. El Ouahdani

Journal volume & issue
Vol. 5, no. 8
p. e02211

Abstract

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In many deterministic methods, concerning the resolution of the neutron transport equation, a more global and practical representation of the angular flux is needed to provide us with useful and complete information on the neutron population in a reactor core. The purpose of this paper is to provide a reference quality calculation for the angular flux. The discrete ordinate method (SN) is processed with a new matrix form which is used to model an isotropic and anisotropic multiplicative system in a region, multi-region for one energy group in a cartesian geometry. The obtained results are compared to those obtained by MCNP6 code.

Keywords