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Report No.

Development of a reliability evaluation method for fatigue-creep interaction failure of an FBR reactor vessel

Takaya, Shigeru ; Okajima, Satoshi ; Asayama, Tai ; Chitose, Hiromasa*; Machida, Hideo*; Yokoi, Shinobu*; Kamishima, Yoshio*

An evaluation method of the occurrence probability of a through-wall crack in a reactor vessel of a fast breeder reactor due to fatigue-creep interaction has been proposed. Input data were prepared for a trial evaluation and the proposed evaluation method was applied. The result was compared with the allowable occurrence probability derived from the safety requirements for FBR.



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