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Report No.
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R&D for introducing advanced fuels contributing to safety improvement of current LWRs FeCrAl, 2; FeCrAl-ODS steels for BWR fuel claddings

Sakamoto, Kan*; Ukai, Shigeharu*; Kimura, Akihiko*; Yamaji, Akifumi*; Kusagaya, Kazuyuki*; Kondo, Takao*; Yamashita, Shinichiro; Fukahori, Tokio

Using the acquired material data by 2016, the feasibility of the reactor core, accident progress relaxation effect at an accident and a severe accident were confirmed by various analysis when Zircaloy replaced to FeCrAl-ODS steel. The results including the post irradiation examination in fiscal year 2017 will be introduced by this presentation.

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