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A Study on Application of Fatigue Correction Factor for Environmental Fatigue Evaluation of Pressurizer Surge Line

가압기 밀림관 환경피로평가를 위한 피로보정계수 적용에 관한 연구

  • 양준석 (한전전력연구원 원자력발전연구소) ;
  • 박치용 (한전전력연구원 원자력발전연구소) ;
  • 강선예 (한국전력기술주식회사 원자로설계개발단)
  • Published : 2009.10.01

Abstract

Nuclear power plants applying for the continued operation over design life are required to address the effects of reactor water environment in fatigue design requirement of the ASME Code. Reactor water environmental effects are generally evaluated by calculating fatigue correction factors on fatigue usage. This paper describes the application for pressurizer surge line of environmental fatigue correction factors and the strain rate impact in the application. From this paper, the environmental fatigue correction factors resulted from the assumption of a step change in temperature are especially compared with those calculated from the data measured during plant startup. As a conclusion of this paper, the design transient conditions applied to the fatigue design may be conservative in case of the environmental fatigue evaluation.

Keywords

Environmental Fatigue;Fatigue Correction Factor;Strain Rate;Design Transient Condition

References

  1. U.S. NRC, July 2006, Draft Regulatory Guide DG-1144, Guidelines for Evaluating Fatigue Analyses Incororating the Life Reduction of Metal Components due to the Effects of the Light-Water Reactor Environment for New Reactors
  2. KINS, 2006, Review Guideline for Continued Operation of PWR Plants
  3. ASME Boiler and Pressure Vessel Code, Section III, Division 1, Subsection NB, 2001, 'Rules for Construction of Nuclear Facility Components, Class 1 Components,' American Society of Mechanical Engineers, New York
  4. Chopra, O. K., 1999, 'Effects of LWR Coolant Environments on Fatigue Design Curves of Austenitic Stainless Steels,' NUREG/CR-5704, ANL-98/31, U.S. Nuclear Regulatory Commission,Washington, DC
  5. 'USA Standard Code for Pressure Piping, Power Piping,' ANSI B31.1 Power Piping Code, American Society ofMechanical Engineers, New York
  6. ANSYS, Version 10.0, 'Finite Element Program', ANSYS Inc., Canonsburg, PA
  7. Higuchi, M., 2005, 'Development of Evaluation Method of Fatigue Damage on Operating Plant Components in Considering Environmental Effect of LWR Coolant,' Materials Reliability Program: Third International Conference on Fatigue in Reactor Components (MRP-151), EPRI, Palo Alto, CA, 1011958
  8. Chopra, O. K., and Shack, W. J., 1998, 'Effects of LWR Coolant Environments on Fatigue Design Curves of Carbon and Low-Alloy Steels, 'NUREG/CR-6583, ANL-97/18, U.S. Nuclear Regulatory Commission, Washington, DC