# Numerical analysis of the neutron multigroup $SP_N$ equations

Abstract : The multigroup neutron $SP_N$ equations, which are an approximation of the neutron transport equation, are used to model nuclear reactor cores. In their steady state, these equations can be written as a source problem or an eigenvalue problem. We study the resolution of those two problems with an $H^1$-conforming finite element method and a Discontinuous Galerkin method, namely the Symmetric Interior Penalty Galerkin method.
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Journal articles
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Cited literature [18 references]

https://hal-cea.archives-ouvertes.fr/cea-02902626
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• HAL Id : cea-02902626, version 1

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Erell Jamelot, François Madiot. Numerical analysis of the neutron multigroup $SP_N$ equations. Comptes Rendus. Mathématique, Centre Mersenne (2020-..) ; Elsevier Masson (2002-2019), 2021, Comptes Rendus. Mathématique, 359 (5). ⟨cea-02902626⟩

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