2305 維持規格の現場適用の高能率化に関する研究(OS5-2 設計と最適化II)

概要

論文の詳細を見る
Codes for nuclear power generation facilities (rules on fitness for service for nuclear power plants) has been developed by the JSME committee in 2004. However, JSME does not endorse any facility in accordance with this code. Users must understand interpret of this code and accept responsibility for using the code. The calculation program for the crack propagation of fatigue and stress corrosion crack (SCC) has been developed in accordance with the operating procedure of the code. The calculation time for out put the life of fatigue (or SCC) is a few minutes. The initial crack depth probability distribution and the probability of detection for crack in pipes have been investigated for support of management of plant pipe life. The developed support program can estimate the reasonable replace time of pipe by using of Probabilistic fracture mechanics (PFM).
社団法人日本機械学会の論文
2007-10-30