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

한국압력기기공학회 (Korean Society of Pressure Vessels and Piping)
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설계기준초과지진 하의 원전 배관 구조건전성 평가를 위한 변형률 기반 방법

Strain-Based Structural Integrity Evaluation Methods for Nuclear Power Plant Piping under Beyond Design Basis Earthquake

  • 이대영 (한국전력기술 미래전력기술연구소) ;
  • 박흥배 (한국전력기술 미래전력기술연구소) ;
  • 김진원 (조선대학교 원자력공학과) ;
  • 류호완 (고려대학교 기계공학부) ;
  • 김윤재 (고려대학교 기계공학부)
  • 투고 : 2016.12.01
  • 심사 : 2016.12.22
  • 발행 : 2016.12.30
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초록

Following the 2011 Fukushima Nuclear Power Plant accident, the IAEA has issued a revised version of the Nuclear Safety Standard for beyond design basis earthquake to consider the core meltdown accident. In Korea, relevant laws and regulations were also revised to consider beyond design basis earthquake to nuclear components. In this paper, CAV, an seismic damage factor that determines the restart of nuclear power plant after operating breakdown earthquake, is proposed for extension to the beyond design basis earthquake. For pipings not satisfying the beyond design basis earthquake condition, several evaluation methods are suggested, such as strain-based evaluation methods, simple nonlinear analysis method and cumulative damage evaluation method.

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참고문헌

  1. IAEA, 2016, IAEA Safety Standard for protecting peoples and the environment, Safety of Nuclear Power Plants: Design, Specific Safety Requirements, No. SSR-2/1 Rev.1.
  2. KOREA Nuclear Safety and Security Commission, 2016, Technical standards and rules for accident management related to reactor facilities.(in korean)
  3. D. Y. Lee, H. B. Park, J. W. Kim, Y-J. Kim, KPVP, Vol.12, No.01, Review of Evaluation Method for Nuclear Power Plant Pipings under Beyond Design Basis Earthquake Condition.
  4. US Nuclear Regulatory Commission, 1997, Regulatory Guide 1.166, Pre-earthquake Planning and Immediate Nuclear Power Plant Operator Post-earthquake Actions.
  5. EPRI, 1991, TR-100082, Standardization of the Cumulative Absolute Velocity.
  6. ASME, 2015, Nonmandatory Appendix FF Strain-Based Acceptance Criteria for Energy-Limited Events.
  7. ASME, 2015, Code Case N-779, Alternative Rules for Simplified Elastic-Plastic Analysis Class 1.
  8. KEPCO E&C, 2016, Annual Report-Development of Crack Assessment Methodology for Aged Main Components of Operating NPPs BDBE Condition and Validation by Simulated Experiment.