講演情報
[2C02]Verification and sensitivity investigation of FRENDY-V2/GENESIS for sodium-cooled fast reactor fuel assembly
*Jun-Shuang Fan1, Tatsuya Fujita1, Go Chiba1 (1. Hokkaido Univ.)
キーワード：
FRENDY Version 2、GENESIS、sodium-cooled fast reactor、neutron current method、JENDL-5
The authors verified the applicability of calculation procedure using the nuclear data processing code FRENDY version 2 and the three-dimensional neutron transport calculation code GENESIS for a sodium-cooled fast reactor fuel assembly. The results of the infinite multiplication factor and the fission reaction rate distribution within the fuel assembly agreed well with those obtained by the Monte Carlo code MVP3. The sensitivity of these calculation results on various calculation options was also analyzed.