Sensitivity Analyses of Failure Probability of Pipes in Nuclear Power Plants using PRO-LOCA
PRO-LOCA를 이용한 원전 배관의 파손확률에 대한 민감도 해석

Young Ki Cho, Sun Hye Kim, Jai Hak Park
2014 Journal of the Korean Society of Safety  
Recently a new version of PRO-LOCA program was released. Using the program, failure probability of pipes can be evaluated considering fatigue and/or stress corrosion crack growth and the effects of various parameters on the integrity of pipes in nuclear power plants can be evaluated quantitatively. The analysis results can be used to establish an inspection plan and to examine the effects of important parameters in a maintenance plan. In this study, sensitivity analyses were performed using the
more » ... performed using the program for several important parameters including sampling method, initial crack size, number of initial fabrication flaws, operation temperature, inspection interval, operation temperature and nominal applied bending stress. The effect of parameters on the leak and rupture probability of pipes was evaluated due to fatigue or stress corrosion crack growth.
doi:10.14346/jkosos.2014.29.3.136 fatcat:srj5ngerhjbnpgut6mmnrmd57a