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....
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

This paper describes the outline of the guidelines on structural reliability evaluation for the passive components of the fast breeder reactor (FBR). The guidelines are now being prepared by the working group for the system based code in the Japan society of mechanical engineers. They consist of five chapters, which are “General rules”, “Reliability evaluation”, “Failure scenario setting”, “Modeling”, and “Failure probability calculation”, respectively. In the chapter of “Reliability evaluation”, the g...
英字タイトル:
Development of Guidelines for Structural Reliability Evaluation for FBR

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 cod...
英字タイトル:
Benchmark Evaluation of Structural Reliability Evaluation Codes for FBR