2021 Fall Meeting

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Oral presentation

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

[3I01-05] Analysis Code Development

Fri. Sep 10, 2021 9:30 AM - 11:00 AM Room I

chair: Satoshi Takeda (Osaka Univ.)

9:30 AM - 9:45 AM

[3I01] Development of FRENDY/MG (3)Automated generation of background cross section set

*Akio Yamamoto1, Tomohiro Endo1, Kenichi Tada2 (1. Nagoya Univ., 2. JAEA)

Keywords:FRENDY/MG, neutron multi-group cross section, background cross section, self-shielding factor

An automated generation capability of background cross section set is implemented to FRENDY/MG, which a generation capability of neutron multi-group cross sections. The present capability enables appropriate interpolation of self-shielding factors for neutron multi-group cross sections.