2020 Fall Meeting

Presentation information

Oral presentation

III. Fission Energy Engineering » 301-1 Reactor Physics, Utilization of Nuclear Data, Criticality Safety

[2H03-06] Analysis Code Development 1

Thu. Sep 17, 2020 10:40 AM - 11:55 AM Room H (Zoom room 8)

Chair:Hiroki Koike(MHI)

11:10 AM - 11:25 AM

[2H05] Investigation of the impact of difference between open nuclear data processing codes on neutron transport calculations

(3)Difference of nuclear data processing method

*Kenichi TADA1, Tadashi IKEHARA1, Michitaka ONO2, Masayuki TOJO2 (1. JAEA, 2. GNF-J)

Keywords:Nuclear data processing, Thermal scattering law data, FRENDY, NJOY, ACE file, MCNP6.1

Comparison of the nuclear data processing code is realized using nuclear data processing code FRENDY which has been developed in JAEA. In this presentation, we explain the difference of nuclear data processing method between FRENDY and NJOY. This presentation also explains the important points to process nuclear data using NJOY.