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
英字タイトル:
Development of a Reliability Evaluation Method for Fatigue-Creep Interaction Failure of an FBR Reactor Vessel 髙屋 茂 Shigeru TAKAYA
著者:
岡島 智史 Satoshi OKAJIMA 浅山 泰 Tai ASAYAMA 千年 宏昌 Hiromasa CHITOSE 町田 秀夫 Hideo MACHIDA 横井 忍 Shinobu YOKOI 神島 吉郎 Yoshio KAMISHIMA
発刊日:
公開日:
Fast Breeder ReactorFatigue-Creep InteractionFRReliabilitySystem Based Code
Development of a Reliability Evaluation Method for Fatigue-Creep Interaction Failure of an FBR Reactor Vessel 髙屋 茂 Shigeru TAKAYA
著者:
岡島 智史 Satoshi OKAJIMA 浅山 泰 Tai ASAYAMA 千年 宏昌 Hiromasa CHITOSE 町田 秀夫 Hideo MACHIDA 横井 忍 Shinobu YOKOI 神島 吉郎 Yoshio KAMISHIMA
発刊日:
公開日:
カテゴリ: 第8回
キーワードタグ:Fast Breeder ReactorFatigue-Creep InteractionFRReliabilitySystem Based Code
概要
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 p repared for a trial evaluation and the proposed evaluation method was applied. The result was c ompared with the allowable occurrence probability derived from the safety requirements for FBR.
