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.

翻译：多群中子扩散方程常用于模拟核反应堆堆芯尺度下的中子密度。传统上，这些方程可转化为混合变分形式。本章提出一种基于后验估计子的自适应网格细化方法。我们聚焦于笛卡尔网格上的细化策略，因为此类结构在核反应堆堆芯应用中十分常见。