Numerical analysis of the neutron multigroup $SP_N$ equations
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...
| Main Authors: | , |
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| Format: | Article |
| Language: | English |
| Published: |
Académie des sciences
2021-07-01
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| Series: | Comptes Rendus. Mathématique |
| Online Access: | https://comptes-rendus.academie-sciences.fr/mathematique/articles/10.5802/crmath.189/ |