Japan Atomic Energy Agency has developed a new nuclear data processing code, named FRENDY, to generate ACE-formatted files from various evaluated nuclear libraries. A code-to-experiment verification of FRENDY processing was carried out in this study with criticality benchmark assessments of the high temperature engineering test reactor. The ACE files of the JENDL-4.0 and ENDF/B-VII.1 was generated successfully by FRENDY. These ACE files have been used in MCNP6 transport for various benchmark problems of the high temperature engineering test reactor. As a result, the k_eff and reaction rate obtained by MCNP6 calculation presented a good agreement compared to the experimental data. The proper ACE files generation by FRENDY was confirmed for the HTTR criticality calculations.

日本原子能机构已经开发了一种名为FRENDY的新核数据处理代码，可以从各种经过评估的核库中生成ACE格式的文件。在这项研究中，对FRENDY工艺进行了代码到实验的验证，并对高温工程测试反应堆进行了临界基准评估。FRENDY已成功生成JENDL-4.0和ENDF / B-VII.1的ACE文件。这些ACE文件已用于MCNP6运输中，用于解决高温工程测试反应堆的各种基准问题。结果，通过MCNP6计算获得的k _eff和反应速率与实验数据相比表现出良好的一致性。由FRENDY生成的正确ACE文件已被确认用于HTTR临界度计算。