Application of Probabilistic Fracture Mechanics Technique Using Monte Carlo Simulation

몬테카를로 시뮬레이션을 이용한 확률론적 파괴역학 수법의 적용성 검토

  • 이준성 (경기대학교 전자기계공학부) ;
  • 곽상록 (성균관대학교 대학원 기계공학부) ;
  • 김영진 (성균관대학교 기계공학부)
  • Published : 2001.10.01

Abstract

For major structural components periodic inspections and integrity assessments are needed for the safety. However, many flaws are undetectable because sampling inspection is carried out during in-service inspection. Probabilistic integrity assessment is applied to take into consideration of uncertainty and variance of input parameters arise due to material properties and undetectable cracks. This paper describes a Probabilistic Fracture Mechanics(PFM) analysis based on the Monte Carlo(MC) algorithms. Taking a number of sampling data of probabilistic variables such as fracture toughness value, crack depth and aspect ratio of an initial surface crack, a MC simulation of failure judgement of samples is performed. for the verification of this analysis, a comparison study of the PFM analysis using a commercial code, mathematical method is carried out and a good agreement was observed between those results.

Keywords

References

  1. 김건영, 壓子哲雄, 강명수, '크리프 균열성장 모델에 대한 확률론적 수명예측 프로그램,' 한국정밀공학회지, 제16권, 제6호, pp. 100-107, 1999
  2. USNRC, 'Reactor Safety Study : An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants,' WASH-1400, NUREG-75/014, 1975
  3. Wells, J.E., George, L.L., and Cummings, G.E., 'Seismic Safety Margins Resarch Program, Phase I Final Report - Systems Analysis, 8,' NUREG/CR-2015, Vol. 8, 1984
  4. USNRC, 'Individual Plant Examination : Submittal Guidance,' NUREG-1335, 1989
  5. Canadian Standard Association, 'Periodic Inspection of CANDU Nuclear Power Plant Components,' CAN/CSA-N285.4, 1994
  6. ASME, 'Rules for In Service Inspection of Nuclear Plant Components,' ASME Boiler and Pressure Vessel Code Sec.XI, Appendix A, 1998
  7. USNRC, 'Investigation and Evaluation of SCC in Piping Fracture Mechanics,' NUREG-CR/6540, 1997
  8. Lawrence Livermore National Laboratory, 'PC-PRAISE : A Probabilistic Fracture Mechanics Computer Code for Piping Reliability Analysis,' NUREG/ CR-5864, 1992
  9. Paris, P. C. an Erdogan, F., 'A Critical Analysis of Crack Propagation Laws,' Trans. ASME, J. Basic Eng. Ind., Vol. D85, 1963
  10. Newman, J. C. and Raju, I. S., 'Stress Intensity Factors for Internal surface cracks in Cylindrical Pressule Vessels,' Transaction of the ASME, Vol. 102, 1980
  11. ASME, 'ASME Boiler and Pressure Vessel Code,' SectionXI, Appendix A-1000, 1992
  12. Zahoor, A., 'Ductile Fracture Hand-book, Vol. I, II, III,' EPRI Report NP-6301-D, Electric Power Research Institute, 1989
  13. 이진석, 김영진, 석창성, 박윤원, 'CANDU 압력관의 건전성평가를 위한 결합해석,' 대한기계학회 논문집, 제19권, 제3호, pp. 731-740, 1995
  14. Law, A.M., Kelton, W.D., 'Simulation Modeling and Analysis,' 2nd Edition, McGraw-Hill, 1991
  15. Lawrence Livermore National Laboratory, 'Probability of Pipe Fracture in the Primary Coolant Loop of a PWR Plant,' NUREG/CR-2189, 1981
  16. Ang, A.H., Tang, W.H., 'Probability Concepts in Engineering Planning Design,' John Wiley & Sons, Vol. I, II, 1975
  17. Ditlevsen, O., Madsen, H.O., 'Structural Reliability Method,' John Wiley & Sons, 1996
  18. Patrick D. T. O'Connor, 'Practical Reliability Engineering,' John Wiley & Sons, 3rd Edition, 1997