Application of the JENDL-4.0 nuclear data set for the uncertainty analysis of the prototype FBR Monju

JENDL-4.0核データのもんじゅ炉心特性解析への適用

此村 守; Tamagno, P.*; 竹田 敏一*; Van Rooijen, W. F. G.*

Konomura, Mamoru; Tamagno, P.*; Takeda, Toshikazu*; Van Rooijen, W. F. G.*

The presentation deals with uncertainty analysis on Monju fast reactor using the JENDL-4.0 nuclear data set and the ERANOS code. For this study, cross-sections library had to be produced for the ERANOS cell code ECCO and verified with the benchmarks MZA and MZB. Monju 2010 restart reactivity measurement was modeled using several libraries. Uncertainty analysis is performed and comparison is done with the former JENDL-3.3 evaluation.