Development of accident tolerant FeCrAl-ODS fuel cladding for BWRs in Japan

K. Sakamoto, Y. Miura,S. Ukai, N.H. Oono,A. Kimura, A. Yamaji, K. Kusagaya, S. Takano, T. Kondo, T. Ikegawa, I. Ioka,S. Yamashita

Journal of Nuclear Materials（2021）

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摘要

The FeCrAl-oxide dispersion strengthened (ODS) alloy is a promising candidate alloy for the accident tolerant fuel (ATF) cladding of light water reactors (LWRs) and has been recently developed in Japan. This paper reports on the progress of the development of accident tolerant FeCrAl-ODS fuel claddings for boiling water reactors (BWRs) in Japan.

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FeCrAl-ODS,ATF,LWR,BWR,Accident,Normal operation

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