Comptes Rendus
Analyse numérique
Numerical analysis of the neutron multigroup SP N equations
[Analyse numérique des équations de la neutronique SP N multigroupe]
Comptes Rendus. Mathématique, Volume 359 (2021) no. 5, pp. 533-545.

Les équations de la neutronique SP N multigroupe, qui sont une approximation de l’équation de transport des neutrons, sont utilisées pour la modélisation des cœurs de réacteurs nucléaires. Dans le cas stationnaire, ces équations sont soit un problème à source, soit un problème aux valeurs propres. Nous étudions l’approximation de ces deux problèmes avec une méthode d’éléments finis conformes dans H 1 et une méthode d’éléments finis discontinus appelée Symmetric Interior Penalty Galerkin.

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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DOI : 10.5802/crmath.189

Erell Jamelot 1 ; François Madiot 2

1 Université Paris-Saclay, CEA, Service de Thermo-hydraulique et de Mécanique des Fluides, 91191, Gif-sur-Yvette, France
2 Université Paris-Saclay, CEA, Service d’Études des Réacteurs et de Mathématiques Appliquées, 91191, Gif-sur-Yvette, France
Licence : CC-BY 4.0
Droits d'auteur : Les auteurs conservent leurs droits
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Erell Jamelot; François Madiot. Numerical analysis of the neutron multigroup $SP_N$ equations. Comptes Rendus. Mathématique, Volume 359 (2021) no. 5, pp. 533-545. doi : 10.5802/crmath.189. https://comptes-rendus.academie-sciences.fr/mathematique/articles/10.5802/crmath.189/

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