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高速増殖炉原子炉容器のクリープ疲労に関する信頼性評価手法の開発

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

高屋 茂; 岡島 智史; 浅山 泰; 千年 宏昌*; 町田 秀夫*; 横井 忍*; 神島 吉郎*

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

高速増殖炉原子炉容器の貫通き裂の発生確率に関する評価手法を提案した。試評価用の入力条件を整備し、提案手法を適用した。評価結果は、安全要求から導出される許容確率と比較した。

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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