Abstract Thermal neutron scattering laws tabulated in File 7 for various materials the ENDF/B database require processing to generate the cross section and distribution data needed for use in Monte Carlo reactor simulations. Typically, the total scattering cross section is calculated on a fixed energy grid and interpolated on this grid. Nevertheless, this method may result in the loss of physical features in the cross section related to the details of the thermal scattering law, especially the oscillatory behavior of solid hydride moderators (e.g., ZrH, YH2). An adaptive energy grid has been implemented in the NDEX nuclear data code, initialized from the tabulated β grid of the processed evaluation. Cross section libraries for Monte Carlo codes generated using this adaptive grid demonstrate greatly improved prediction of oscillations in solid metal hydride moderators when compared to the fixed grid method.

中文翻译：

---

在 NDEX 中实现自适应能量网格程序，用于处理热中子散射截面

摘要 文件 7 中列出的热中子散射定律适用于 ENDF/B 数据库需要处理的各种材料，以生成用于蒙特卡罗反应堆模拟所需的横截面和分布数据。通常，总散射截面是在固定能量网格上计算的，并在该网格上进行插值。然而，这种方法可能会导致与热散射定律细节相关的横截面物理特征的丢失，尤其是固体氢化物减速剂（例如，ZrH、YH2）的振荡行为。在 NDEX 核数据代码中实施了自适应能源网格，从处理评估的列表 β 网格初始化。