Nuclear data processing code FRENDY: A verification with HTTR criticality benchmark experiments

Nozomu Fujimoto, Kenichi Tada, Hai Quan Ho, Shimpei Hamamoto, Satoru Nagasumi, Etsuo Ishitsuka

研究成果: Contribution to journalArticle査読

抄録

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 keff 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.

本文言語英語
論文番号108270
ジャーナルAnnals of Nuclear Energy
158
DOI
出版ステータス出版済み - 8 2021

All Science Journal Classification (ASJC) codes

  • 原子力エネルギーおよび原子力工学

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