R&D of advanced stainless steels for BWR fuel claddings, 3-2; Applicability of MOX fuel core design

Takano, Sho*; Goto, Daisuke*; Kusagaya, Kazuyuki*; Sakamoto, Kan*; Yamashita, Shinichiro   

For practical use of FeCrAl-ODS stainless steel, it is necessary to confirm that a design request in a reactor core is achieved even if the loss of neutron economy is caused by the big neutron absorption cross section. In previous study, the core design was established in the case of cladding thickness of 0.3 mm, water rod thickness of 0.3 mm and channel box thickness of 1.0 mm. In this report, the core property was evaluated when FeCrAl-ODS stainless steel and MOX fuel were applied.