NTP-ERSN: A new package for solving the multigroup neutron transport equation in a slab geometry

Lahdour, M.; Bardouni, T. El; Chakir, E.; Benaalilou, K.; Mohammed, Maged; Bougueniz, H.; Yaakoubi, H. El

doi:10.1016/j.apradiso.2018.12.004

Cited by 9 publications

(1 citation statement)

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“…This is why it is relatively common in neutronics that the term SboldN method implicitly implies a diamond difference scheme. For the sake of brevity, we limit our discussion to steady-state transport equation for monoenergetic neutrons in a slab geometry (Lahdour et al, 2019) for which the transport equation is reduced toμdψfalse(x,μfalse)dxbadbreakafter+normalΣtfalse(xfalse)ψfalse(x,μfalse)goodbreakafter=Qfalse(x,μfalse) where:…”

Section: Methodsmentioning

confidence: 99%

The discrete ordinate method for angular flux calculations in slab geometry

Lahdour

Bardouni

Mohammed

et al. 2019

Heliyon

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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 (S ) 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.

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