Refine your search:     
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.



- Accesses





[CLARIVATE ANALYTICS], [WEB OF SCIENCE], [HIGHLY CITED PAPER & CUP LOGO] and [HOT PAPER & FIRE LOGO] are trademarks of Clarivate Analytics, and/or its affiliated company or companies, and used herein by permission and/or license.