Since the nuclear data forms a vital component in reactor physics computations, the nuclear community needs processing codes as tools for translating the Evaluated Nuclear Data Files (ENDF) to simulate nuclear-related problems such as an ACE format that is used for MCNP. Errors, inaccuracies or discrepancies in library processing may lead to a calculation that disagrees with the experimentally measured benchmark. This paper provides an overview of the processing and preparation of ENDF/B-VIII.0 incident neutron data with NECP-Atlas and NJOY codes for implementation in the MCNP code. The resulting libraries are statistically inter-compared and tested by conducting benchmark calculations, as the mutual-comparison is a source of strong feedback for further improvements in processing procedures. The database of the benchmark experiments is based on a selection taken from the International Handbook of Evaluated Criticality Safety Benchmark Experiments (ICSBEP handbook) and those proposed by Russell D. Mosteller. In general, there is quite good agreement between the NECP-Atlas1.2 and NJOY21^(1.0.0.json) results with no substantial differences, if the correct input parameters are used.

由于核数据是反应堆物理计算中的重要组成部分，因此核界需要处理代码作为转换评估核数据文件 (ENDF) 的工具，以模拟与核相关的问题，例如用于 MCNP 的 ACE 格式。库处理中的错误、不准确或差异可能导致计算与实验测量的基准不一致。本文概述了使用 NECP-Atlas 和 NJOY 代码处理和准备 ENDF/B-VIII.0 入射中子数据，以便在 MCNP 代码中实现。由此产生的库通过进行基准计算进行统计上的相互比较和测试，因为相互比较是进一步改进处理程序的强烈反馈的来源。基准实验的数据库基于选自评估临界安全基准实验国际手册 (ICSBEP 手册) 和 Russell D. Mosteller 提出的那些内容。总的来说，NECP-Atlas1.2 和 NJOY21 之间有很好的一致性^(1.0.0.json)结果没有实质性差异，如果使用正确的输入参数。