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

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 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.