[3D06-09] Pu-Thermal Reactor

11:05 AM - 11:20 AM JST(2:05 AM - 2:20 AM UTC)

[3D07] Future prospects of advanced pluthermal operation for BWR based on domestic reprocessing(2) Application of ATF cladding to high burnup 10x10 MOX fuel

*Manabu Yoshida¹, Daisuke Goto¹, Kazuhiko Matsumura¹, Tsugumi Tsuchida¹, Junji Matsunaga¹ (1. GNF-J)

Keywords:

Atomic energy,Plutonium thermal operation,BWR,ATF,J-MOX

Accident Tolerant Fuel (ATF) has been actively studied to mitigate the effects of accidents in light water reactors. One of the ATF cladding materials for BWR that has been studied is FeCrAl-ODS, which has been shown to reduce hydrogen generation during accidents. In addition, while it has the disadvantage of having a larger thermal neutron absorption cross section than zircaloy because it is mainly composed of Fe, it has the feature of reducing the cladding thickness and increasing the volume in the fuel rods. These features are suitable for MOX fuels, which have a hard neutron spectrum and have advantages when the fuel pellet loading is increased. In this study, 10×10 ATF-MOX fuel with FeCrAl-ODS cladding was used as GNF3 fuel, and MOX pellets in the enrichment range supplied from the J-MOX Plant were loaded in the fuel rods. In this study, GNF-J evaluated the fuel cycle characteristics of BWR5 and ABWR under various operating conditions.