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      탄소성 변형률 기반 내진성능 평가 절차서 개발 방안 = A Plan to Develop Seismic Capacity Verification Procedures Based on the Elastic-Plastic Strain Features

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      https://www.riss.kr/link?id=A105989143

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      A development plan for seismic capacity verification procedures of nuclear components based on the elastic-plastic strain (EPS) features is explained in this paper. The EPS methodology is more realistic to assess seismic responses of components to ext...

      A development plan for seismic capacity verification procedures of nuclear components based on the elastic-plastic strain (EPS) features is explained in this paper. The EPS methodology is more realistic to assess seismic responses of components to extreme seismic events beyond the safe shutdown earthquake (SSE) than current practices with the criteria of stress limits. The EPS based approach to analyze the seismic capacity of components can reduce over-conservatism in the current stress-based criteria and can incorporate the seismic responses of components deformed in plastic behavior by the motion of extreme earthquake.

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      참고문헌 (Reference)

      1 이대영, "설계기준초과지진 하의 원전 배관 구조건전성 평가를 위한변형률 기반 방법" 한국압력기기공학회 12 (12): 66-70, 2016

      2 MOTIE, "The Second Plan for National Energy Supply" 2014

      3 Morishita, M, "Seismic Qualification of Piping Systems by Detailed Inelastic Response Analysis, Part 1- A Code Case for Piping Seismic Evaluation Based on Detailed Inelastic Response Analysis" 2017

      4 KEPIC MNB, "Nuclear Mechanical, Class 1 Components" Korea Electric Association 2015

      5 "NSSC No. 17, 2016, Regulations on Technical Standards for Nuclear Reactor Facilities"

      6 Hwang, J. K, "Lessons Learned from Seismic Fragility Tests of Nuclear Piping Systems" 69-72, 2018

      7 "KEPIC END 2000, 2015, Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations"

      8 "KEPIC END 1100, 2015, “Qualifying Class 1E Equipment for Nuclear Power Generating Stations"

      9 EPRI, "Guidelines for development of in-cabinet amplified response spectra for electrical benchboards and panels" Electric Power Research Institute 1990

      10 EPRI, "Guidelines for Development of In-Cabinet Seismic Demand for Devices Mounted in Electrical Cabinets" Electric Power Research Institute 1995

      1 이대영, "설계기준초과지진 하의 원전 배관 구조건전성 평가를 위한변형률 기반 방법" 한국압력기기공학회 12 (12): 66-70, 2016

      2 MOTIE, "The Second Plan for National Energy Supply" 2014

      3 Morishita, M, "Seismic Qualification of Piping Systems by Detailed Inelastic Response Analysis, Part 1- A Code Case for Piping Seismic Evaluation Based on Detailed Inelastic Response Analysis" 2017

      4 KEPIC MNB, "Nuclear Mechanical, Class 1 Components" Korea Electric Association 2015

      5 "NSSC No. 17, 2016, Regulations on Technical Standards for Nuclear Reactor Facilities"

      6 Hwang, J. K, "Lessons Learned from Seismic Fragility Tests of Nuclear Piping Systems" 69-72, 2018

      7 "KEPIC END 2000, 2015, Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations"

      8 "KEPIC END 1100, 2015, “Qualifying Class 1E Equipment for Nuclear Power Generating Stations"

      9 EPRI, "Guidelines for development of in-cabinet amplified response spectra for electrical benchboards and panels" Electric Power Research Institute 1990

      10 EPRI, "Guidelines for Development of In-Cabinet Seismic Demand for Devices Mounted in Electrical Cabinets" Electric Power Research Institute 1995

      11 USNRC, "Evaluation of JNES Equipment Fragility Tests for Use in SPRA for US NPPs" U.S. Nuclear Regulatory Commission 2011

      12 Yang, H, "Energy Dissipation Analysis of Elastic-Plastic Materials" 331 : 309-326, 2017

      13 An Utility, "Development of Technology for Structural Integrity Evaluation of Major Components, A Private propriety"

      14 Kim, J. S, "Development of Effective Elastic-Plastic Dynamic Analysis and Strain Based Assessment for Time History Seismic Analysis of Major Components of Nuclear Power Plants" 2017

      15 EPZ, "Complementary Safety Margin Assessment, Final Report" 2.26-2.30, 2011

      16 Adams, T. M, "Basis of the Upcoming Changes to Piping Seismic Design Rules in the ASME BPVC Section III, Division 1, Article NB-3200" 2015

      17 "ASME BPVC Sec. VIII Part 5, 2015, “Design by Analysis Requirements,”"

      18 "ASME BPVC Sec. III Div.1 Sub. NB, 2017, “Rules for Construction of Nuclear Facility Components"

      19 "ASME BPVC Sec. III App.FF, 2017, “Strain-Based Acceptance Criteria for Energy-Limited Events,”"

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      연월일 이력구분 이력상세 등재구분
      2023 평가예정 계속평가 신청대상 (계속평가)
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