高速炉機器の構造信頼性評価法のベンチマーク評価
英字タイトル:
Benchmark Evaluation of Structural Reliability Evaluation Codes for FBR
著者:
髙屋 茂 Shigeru TAKAYA 浅山 泰 Tai ASAYAMA 町田 秀夫 Hideo MACHIDA 神島 吉郎 Yoshio KAMISHIMA
発刊日:
公開日:
Crack propagationDeterministic evaluationFast breeder reactorFatigue-creep interaction damageProbabilistic evaluationReactor vesselSystem based code
Benchmark Evaluation of Structural Reliability Evaluation Codes for FBR
著者:
髙屋 茂 Shigeru TAKAYA 浅山 泰 Tai ASAYAMA 町田 秀夫 Hideo MACHIDA 神島 吉郎 Yoshio KAMISHIMA
発刊日:
公開日:
カテゴリ: 第11回
キーワードタグ:Crack propagationDeterministic evaluationFast breeder reactorFatigue-creep interaction damageProbabilistic evaluationReactor vesselSystem based code
概要
Abstract This paper describes a procedure of structural reliability evaluation of passive components of fast breeder reactors for a failure due fatigue-creep interaction damage, and also reports results of benchmark evaluation conducted by using two independently developed codes. The s tructural integrity of a reactor vessel was evaluated deterministically and probabilistically. The results estimated by two codes agree well for oth of deterministic and probabilistic evaluations, which shows that these codes are programmed properly according to the evaluation procedure.
