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Nuclear data processing code FRENDY; A Verification with HTTR criticality benchmark experiments

核データ加工コードFRENDY; HTTR臨界ベンチマーク実験を用いた検証

藤本 望*; 多田 健一  ; Ho, H. Q.  ; 濱本 真平 ; 長住 達; 石塚 悦男  

Fujimoto, Nozomu*; Tada, Kenichi; Ho, H. Q.; Hamamoto, Shimpei; Nagasumi, Satoru; Ishitsuka, Etsuo

Japan Atomic Energy Agency has developed a new nuclear data processing code, namely FRENDY, to generate the ACE files from various 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 transportation calculation for various benchmark problems of the high temperature engineering test reactor. As a result, the k$$_{rm  eff}$$ 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.

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分野:Nuclear Science & Technology

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