[Analyse numérique des équations de la neutronique multigroupe]
Les équations de la neutronique 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 et une méthode d’éléments finis discontinus appelée Symmetric Interior Penalty Galerkin.
The multigroup neutron 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 -conforming finite element method and a Discontinuous Galerkin method, namely the Symmetric Interior Penalty Galerkin method.
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Erell Jamelot 1 ; François Madiot 2
CC-BY 4.0
@article{CRMATH_2021__359_5_533_0,
author = {Erell Jamelot and Fran\c{c}ois Madiot},
title = {Numerical analysis of the neutron multigroup $SP_N$ equations},
journal = {Comptes Rendus. Math\'ematique},
pages = {533--545},
publisher = {Acad\'emie des sciences, Paris},
volume = {359},
number = {5},
year = {2021},
doi = {10.5802/crmath.189},
language = {en},
}
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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