Numerical Analysis Of The Neutron Multigroup Spn Equations

The multigroup neutron SPN 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.