한국압력기기공학회 논문집 (Transactions of the Korean Society of Pressure Vessels and Piping)

한국압력기기공학회 (Korean Society of Pressure Vessels and Piping)
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ASME BPVC Section XI Appendix L의 결함허용평가에 따른 허용운전주기 민감도 분석

Sensitivity Analysis for Allowable Operating Period Based on the Flaw Tolerance Evaluation of ASME BPVC Section XI Appendix L

  • 투고 : 2021.11.16
  • 심사 : 2021.12.20
  • 발행 : 2021.12.31
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초록

During operation of nuclear power plants, the fatigue assessment should be conducted repeatedly, considering changes of operating environments. For the case that cumulative usage factors (CUFs) may exceed the acceptance limit, flaw tolerance evaluation can be an alternative method to meet the regulatory requirements. In this respect, this paper analyzes the effects of the input variables for flaw tolerance evaluation based on ASME BPVC Section XI Appendix L. The reference analysis is performed for the example problem in NUREG/CR-6934. Then effects of the crack orientation, stress intensity factor solutions, thermal stress profiles, fatigue stress decomposition and fatigue crack growth curves are considered for the sensitivity analysis. The results show that the stress analysis considering the actual environment plays a crucial role in flaw tolerance evaluation.

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과제정보

본 연구는 원자력안전위원회의 재원으로 한국원자력안전재단의 지원을 받아 수행한 원자력안전연구사업의 연구결과입니다. (No. 1805005)

참고문헌

  1. ASME BPVC Section III, Division 1, NB, "Class 1 Components," American Society of Mechanical Engineers, NY.
  2. Lee, Y.S., Kim, T.S., Lee, J.G., 2010, "Fatigue Life Analysis of SA508 Gr. 1A Low-Alloy Steel under the Operating Conditions of Nuclear Power Plant," Trans. of the KPVP, Vol. 6, No. 1, pp. 50-56.
  3. Lee, H.B., Kim, H.S., Kim, T., Jang, C., 2017, "Environmental Fatigue Behaviors of Austenitic Stainless Steels in the Primary Water Environment of Nuclear Power Plant," Trans. of the KPVP, Vol. 13, No. 2, pp. 19-20.
  4. KINS, 2015, "Fatigue assessment for new nuclear power plants regarding environmentally assisted life reduction of metal components," Korea Institute of Nuclear Safety, Daejeon, KINS/RG-N05.04.
  5. USNRC, 2018, "Guidelines for evaluating the effects of light-water reactor water environments in fatigue analyses of metal components," U.S. Nuclear Regulatory Commission, Washington, DC, Regulatory Guide 1.207, Revision 1.
  6. USNRC, 2018, "Effect of LWR coolant environments on the fatigue life of reactor materials," U.S. Nuclear Regulatory Commission, Washington, DC, NUREG/CR-6909, Revision 1.
  7. ASME BPVC Section XI, Nonmandatory Appendix L, 2008, "Operating Plant Fatigue Assessment," American Society of Mechanical Engineers, NY.
  8. USNRC, 2013, "Turkey point nuclear generating Units 3 and 4 - Review of license renewal commitment for pressurizer surge line welds inspection program," U.S. Nuclear Regulatory Commission, Washington, DC.
  9. Florida Power & Light Company, 2018, "Turkey Point Nuclear Plant Units 3 and 4 Subsequent License Renewal Application. Subsequent license renewal application," Revision 1, U.S. Nuclear Regulatory Commission, Washington, DC. (NRC ADAMS Accession No. ML18113A146)
  10. ASME BPVC Section XI, Nonmandatory Appendix A, "Analytical Evaluation of Flaws," American Society of Mechanical Engineers, NY.
  11. ASME, Section XI, Nonmandatory Appendix C, "Analytical Evaluation of Flaws in Piping," American Society of Mechanical Engineers, NY.
  12. USNRC, 2007, "Fatigue crack flaw tolerance in nuclear power plant piping: A basis for improvements to ASME Code Section XI Appendix L," U.S. Nuclear Regulatory Commission, Washington, DC, NUREG/CR-6934.
  13. ASME Section XI, Subsection IWB, "Requirements for Class 1 Components of Light-Water-Cooled Plants," American Society of Mechanical Engineers, NY.
  14. USNRC, 2000, "Fatigue analysis of components for 60-year plant life," U.S. Nuclear Regulatory Commission, Washington, DC, NUREG/CR-6674.
  15. ASME BPVC Section XI, Case N-809, 2017, "Reference Fatigue Crack Growth Rate Curves for Austenitic Stainless Steels in Pressurized Water Reactor Environments," American Society of Mechanical Engineers, NY.