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Report No.

Fast Breeder Reactor core design study using JENDL-4.0

Ohgama, Kazuya; Oki, Shigeo; Okubo, Tsutomu

The core characteristics of a sodium-cooled Fast Breeder Reactor (FBR) with 750 MWe output were evaluated by using the fast reactor cross section set JFS-3-J4.0, which was generated by the new Japanese nuclear data library JENDL-4.0. The core characteristics were compared with those obtained by using the former fast reactor cross section set JFS-3-J3.3 in order to investigate differences between the both results. Effects on the core characteristics caused by differences in cross sections of important reactions and nuclides in the cross section sets were analyzed.



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