[2I04-07] Development of Nuclear Data Processing Code

[2I04] Investigation of the impact of difference between open nuclear data processing codes on neutron transport calculations

(1)Overview of comparison of nuclear data processing

*Kenichi Tada¹, Tadashi Ikehara¹, Michitaka Ono², Masayuki Tojo² (1. JAEA, 2. GNF-J)

Keywords:FRENDY, NJOY, nuclear data processing, independent verification, ACE library, Reliability of simulation

Comparison of the nuclear data processing code is realised using nuclear data processing code FRENDY which has been developed in JAEA. In this study, we compared the difference of the nuclear data processing codes between FRENDY and NJOY. The impact of difference between open nuclear data processing codes on neutron transport calculations were also investigated. In this presentation, the difference of the nuclear data processing method between FRENDY and NJOY and ACE verification project carried out by IAEA.