DOI QR코드

DOI QR Code

Complex Leakage Probability Evaluation of Nuclear Pipes by Fatigue and Stress Corrosion Cracking

피로 및 응력부식균열에 의한 원전 배관의 복합누설확률 평가

  • Received : 2015.08.25
  • Accepted : 2015.11.25
  • Published : 2015.12.30

Abstract

In the present study, complex leakage probabilities of nuclear pipes due to fatigue and stress corrosion cracking are evaluated by using the PINTIN(Piping INTegrity INner flaws) that is developed based on the existing PRAISE(Piping Reliability Analysis Including Seismic Events) program. With regard to the aging and crack instability, small leak and big leak probabilities are calculated for several pipes in a reactor coolant system of domestic nuclear plant. Moreover, sensitivity analysis is also performed to find out the effect of parameters for the leakage of pipes, which shows the coolant temperature is the most influencing parameter.

Keywords

References

  1. NRC, "Guidance for Performance-Based Regulation", NUREG/BR-0303, 2002.
  2. D. Datta, "Development of an Advanced PFM Code for the Integrity Evaluation of Nuclear Piping System under Combined Aging Mechanisms", Ph.D. thesis, KAIST, 2010.
  3. NRC, "Theoretica1 and User's Manual for pc PRAISE, A Probabilistic Fracture Mechanics Computer Code for Piping Reliability Analysis, NUREG/CR-5864, 1992.
  4. 박재학, 이재봉, 최영환, "원전배관의 파손확률평가를 위한 P-PIE 프로그램의 개발", 한국안전학회지, 제25권, 제 6호, pp. 1-8, 2010.
  5. 박재학, 이재봉, 최영환, "원자력 발전소 배관의 응력부식에 의한 파손확률 해석", 한국안전학회지, 제26권, 제 2호, pp. 6-12, 2011.