Journal of the Korean Society of Safety (한국안전학회지)

The Korean Society of Safety (한국안전학회)
권호 표지
DOI QR코드

DOI QR Code

Sensitivity Analyses of Failure Probability of Pipes in Nuclear Power Plants using PRO-LOCA

PRO-LOCA를 이용한 원전 배관의 파손확률에 대한 민감도 해석

  • Cho, Young Ki (Department of Safety Engineering, Chungbuk National University) ;
  • Kim, Sun Hye (Department of Mechanical & Material Engineering, Korea Institute of Nuclear Safety) ;
  • Park, Jai Hak (Department of Safety Engineering, Chungbuk National University)
  • 조영기 (충북대학교 안전공학과) ;
  • 김선혜 (한국원자력안전기술원 기계재료평가실) ;
  • 박재학 (충북대학교 안전공학과)
  • Received : 2014.02.25
  • Accepted : 2014.05.08
  • Published : 2014.06.30
Download PDF
⟨ Previous Next ⟩

Abstract

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 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.

Keywords

References

  1. D.O. Harris and D. Dedhia, Win-PRAISE 98 : PRAISE Code in Windows, Technical Report TR-98-4-1, Engineering Mechanics Technology, Inc., 1998.
  2. J. H. Park, J. B. Lee and Y. H. Choi, "Development of a Probabilistic Integrity Assessment Program for Pipes," KSME, Spring Conference, 2009.
  3. Y. K. Cho and J. H. Park, "Effects of Crack Growth Equations and Leak Rate on Failure Probability of Pipes in Nuclear Power Plants," KSME, Spring conference, 2013.
  4. S. H. Kim, J. S. Park, J. S. Kim, J. H. Lee, E. S. Yun, J. S. Yang, J. G. Lee, H. S. Park, Y. J. Oh, S. Y. Kang, K. S. Yoon and J. H. Park, "Current Status of an International Co-Operative Research Program, PARTRIDGE (Probabilistic Analysis as a Regulatory Tool for Risk-Informed Decision Guidance)," Transactions of the Korean Society of Pressure Vessels and Piping, Vol. 9, No. 1, 2013.
  5. PRO-LOCA, 2012, V. 3.7.
  6. P. Scott, R. Kurth, A. Cox, R. Olson and D. Rudland, PRO-LOCA-GUI user's Guide, BATTELLE, 2009.
  7. W. Shack and T. F. Kassner, "Review of Environmental Effects on Fatigue Crack Growth of Austenitic Stainless Steels," NUREG/CR-6176, ANL-94/1, 1994.
  8. L. A. James and D. P. Jones, "Fatigue Crack Growth Correlation for Austenitic Stainless Steels in Air," Proc. Conf. on Predictive Capabilities in Environmentally- Assisted Cracking, R. Rungta, ed., PVP Vol. 99, American Society of Mechanical Engineers, NY, pp. 363-414, 1985.
  9. W. J. Shack, "Environmentally Assisted Cracking in Light Water Reactors: Semiannual Report, July-December 1999," NUREG/CR.4667 Vol. 29, ANL.00/23, pp. 47-64, 2000.
  10. Sensitivity Analyses Results PRO-LOCA Version 3.7 November 2012, BATTELLE, 2012.