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Report No.
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R&D of advanced stainless steels for BWR fuel claddings, 7; Irradiation behavior evaluation

Yamashita, Shinichiro   ; Kondo, Keietsu  ; Aoki, So  ; Hashimoto, Naoyuki*; Ukai, Shigeharu*; Sakamoto, Kan*; Hirai, Mutsumi*; Kimura, Akihiko*; Kusagaya, Kazuyuki*

As the lesson learned from the accident at the Fukushima Daiichi Nuclear Power Station, it is commonly recognized that development of the advanced fuel and core components with enhanced accident tolerance and high reliability is quite important for increasing safety of the existing Light Water Reactors (LWRs). FeCrAl-ODS steel is one of prospective candidate materials with enhanced accident tolerance and needs to be accumulated properly and efficiently fundamental and practical data for core and plant design of nuclear reactor. In this study, hardness measurement and microstructural observation for ion-irradiated FeCrAl-ODS steel were conducted in order to evaluate irradiation property in advance toward a research reactor irradiation test. The results indicated that steep irradiation hardening occurred at the initial stage of irradiation and also that nucleation and growth of irradiation defect cluster occurred at the higher dose than the irradiation hardening occurred.

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