Adaptive mesh refinement on Cartesian meshes applied to the mixed finite element discretization of the multigroup neutron diffusion equations
Numerical Analysis
2025-03-18 v1 Numerical Analysis
Abstract
The multigroup neutron diffusion equations are often used to model the neutron density at the nuclear reactor core scale. Classically, these equations can be recast in a mixed variational form. This chapter presents an adaptive mesh refinement approach based on a posteriori estimators. We focus on refinement strategies on Cartesian meshes, since such structures are common for nuclear reactor core applications.
Keywords
Cite
@article{arxiv.2503.11800,
title = {Adaptive mesh refinement on Cartesian meshes applied to the mixed finite element discretization of the multigroup neutron diffusion equations},
author = {Patrick Ciarlet, and Minh-Hieu Do and François Madiot},
journal= {arXiv preprint arXiv:2503.11800},
year = {2025}
}
Comments
This preprint corresponds to the Chapter 19 of volume 60 in AAMS, Advances in Applied Mechanics (to appear)