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arXiv · 2503.11800

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

Patrick Ciarlet, Jr.·Minh-Hieu Do·François Madiot
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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.

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Patrick Ciarlet, Jr., Minh-Hieu Do, François Madiot. 2025-03-14. Adaptive mesh refinement on Cartesian meshes applied to the mixed finite element discretization of the multigroup neutron diffusion equations. https://arxiv.org/abs/2503.11800

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