Adaptive mesh refinement on Cartesian meshes applied to the mixed finite element discretization of the multigroup neutron diffusion equations

Patrick Ciarlet, Minh Hieu Do, François Madiot

Research output: Chapter in Book/Report/Conference proceedingChapterpeer-review

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.

Original languageEnglish
Title of host publicationAdvances in Applied Mechanics
PublisherAcademic Press Inc.
Pages201-234
Number of pages34
DOIs
Publication statusPublished - 1 Jan 2025

Publication series

NameAdvances in Applied Mechanics
Volume60
ISSN (Print)0065-2156

Keywords

  • A posteriori error estimates
  • Diffusion equation
  • Mesh refinement
  • Mixed formulation
  • Neutronics

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