Development and Application of Detailed Procedure to Evaluate Fatigue Integrity for Major Components Considering Operating Conditions in the Nuclear Power Plant

원전 운전환경을 고려한 주기기 피로 건전성 상세평가 절차개발 및 적용

  • Kim, Byong-Sup (Nuclear Engineering & Technology Institute, Korea Hydro Nuclear Power Company Ltd.) ;
  • Kim, Tae-Soon (Nuclear Engineering & Technology Institute, Korea Hydro Nuclear Power Company Ltd.)
  • 김병섭 (한국수력원자력(주) 원자력발전기술원) ;
  • 김태순 (한국수력원자력(주) 원자력발전기술원)
  • Published : 2006.12.31


In the design of class 1 components to apply ASME code section III NB, a fatigue is considered as one of the important failure mechanisms. Fatigue analysis procedure and standard fatigue design curve(S-N curve) is suggested in ASME code, which had to be performed to meet the integrity of components at the design step. As the plant life extension for operating power plants and the long-lived plant design, however, are being progressed, the fact which the existing ASME fatigue design curve can not consider fatigue effects sufficiently comes to the fore. To find the technical solution for these problems, a number of researches and discussion are continued up to now. In this study, the detailed fatigue analyses using the 3 dimensional modeling for the fatigue-weakened components were performed to develop the optimized fatigue analysis procedure and their results are compared with other reference solutions.


  1. ASME B & PV Code Section III, 'Rules for Construction of Nuclear Power Plant Component', 1998 Edition, 1998
  2. S. Majumdar, O. K. Chopra and W. J. Shack, 'Interim Fatigue Design Curves for Carbon, Low-alloy, and Austenitic Stainless Steel in LWR Environments', NUREG/CR-5999, 1993
  3. A. G. Ware, D. K. Morton and M. E. Nitzel, 'Application of NUREG/CR-5999 Interim Fatigue Curves 0to Selected Nuclear Power Plant Components', NUREG/CR-6260, 1995
  4. J. Keisler, O. K. Chopra and W. J. Shack, 'Fatigue Strain-Life Behavior of Carbon and Low-Alloy Steels, Austenitic Stainless Steels, and Alloy 600 in LWR Environments', NUREG/CR-6335, 1995
  5. O. K. Chopra and W. J. Shack, 'Low-cycle Fatigue of Piping and Pressure Vessel Steels in LWR Environments', Nuclear Engineering and Design, Vol. 184, pp. 49-76, 1998
  6. Jack P. Holman, 'Heat Transfer' 6th Edition, McGraw- Hill Inc.,1986
  7. R. E. Peterson, 'Stress Concentration Design Factors' John Willey and Sons Inc., 1974