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.