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      지진격리된 원전배관의 지진취약도 분석 = Seismic Fragility Analysis of Base Isolated NPP Piping Systems

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      https://www.riss.kr/link?id=A103987799

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      다국어 초록 (Multilingual Abstract)

      Base isolation is considered as a seismic protective system in the design of next generation Nuclear Power Plants (NPPs). If seismic isolation devices are installed in nuclear power plants then the safety under a seismic load of the power plant may be improved. However, with respect to some equipment, seismic risk may increase because displacement may become greater than before the installation of a seismic isolation device. Therefore, it is estimated to be necessary to select equipment in which the seismic risk increases due to an increase in the displacement by the installation of a seismic isolation device, and to perform research on the seismic performance of each piece of equipment. In this study, modified NRC-BNL benchmark models were used for seismic analysis. The numerical models include representations of isolation devices. In order to validate the numerical piping system model and to define the failure mode, a quasi-static loading test was conducted on the piping components before the analysis procedures. The fragility analysis was performed by using the results of the inelastic seismic response analysis. Inelastic seismic response analysis was carried out by using the shell finite element model of a piping system considering internal pressure. The implicit method was used for the direct integration time history analysis. In addition, the collapse load point was used for the failure mode for the fragility analysis.
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      Base isolation is considered as a seismic protective system in the design of next generation Nuclear Power Plants (NPPs). If seismic isolation devices are installed in nuclear power plants then the safety under a seismic load of the power plant may be...

      Base isolation is considered as a seismic protective system in the design of next generation Nuclear Power Plants (NPPs). If seismic isolation devices are installed in nuclear power plants then the safety under a seismic load of the power plant may be improved. However, with respect to some equipment, seismic risk may increase because displacement may become greater than before the installation of a seismic isolation device. Therefore, it is estimated to be necessary to select equipment in which the seismic risk increases due to an increase in the displacement by the installation of a seismic isolation device, and to perform research on the seismic performance of each piece of equipment. In this study, modified NRC-BNL benchmark models were used for seismic analysis. The numerical models include representations of isolation devices. In order to validate the numerical piping system model and to define the failure mode, a quasi-static loading test was conducted on the piping components before the analysis procedures. The fragility analysis was performed by using the results of the inelastic seismic response analysis. Inelastic seismic response analysis was carried out by using the shell finite element model of a piping system considering internal pressure. The implicit method was used for the direct integration time history analysis. In addition, the collapse load point was used for the failure mode for the fragility analysis.

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      참고문헌 (Reference)

      1 최인길, "스펙트럼 형상이 원전 기기 지진취약도에 미치는 영향 평가" 한국지진공학회 7 (7): 23-30, 2003

      2 김정한, "스펙트럼 적합 입력지반운동에 의한 면진구조의 응답 특성" 한국지진공학회 17 (17): 89-95, 2013

      3 김민규, "면진장치를 설치한 회전기기의 지진취약도 개선효과 분석" 한국지진공학회 11 (11): 69-78, 2007

      4 American Society of Mechanical Engineers, "Welded and Seamless Wrought Steel Pipe"

      5 U.S Nuclear Regulatory Commission, "Technical Considerations for Seismic Isolation of Nuclear Facilities(Draft);"

      6 Touboul F, "Seismic behaviour of piping systems with and without detect : experimental and numerical evaluations" 192 : 243-260, 1999

      7 Huang YN, "Seismic Performance Assessment of Base-isolated Safety-related Nuclear Structures" 39 : 1421-1442, 2010

      8 American Society of Civil Engineers, "Seismic Design Criteria for Structures, Systems, and Components in Nuclear Facilities" ASCE

      9 American Society of Civil Engineers, "Seismic Analysis of Safety-Related Nuclear Structures and Commentry" ASCE 2000

      10 KEPCO Engineering & Construction Company, Inc, "SKN 3 & 4 Safety Related-Plant Manual-Main Stem System (MS), 9-521-M442-001"

      1 최인길, "스펙트럼 형상이 원전 기기 지진취약도에 미치는 영향 평가" 한국지진공학회 7 (7): 23-30, 2003

      2 김정한, "스펙트럼 적합 입력지반운동에 의한 면진구조의 응답 특성" 한국지진공학회 17 (17): 89-95, 2013

      3 김민규, "면진장치를 설치한 회전기기의 지진취약도 개선효과 분석" 한국지진공학회 11 (11): 69-78, 2007

      4 American Society of Mechanical Engineers, "Welded and Seamless Wrought Steel Pipe"

      5 U.S Nuclear Regulatory Commission, "Technical Considerations for Seismic Isolation of Nuclear Facilities(Draft);"

      6 Touboul F, "Seismic behaviour of piping systems with and without detect : experimental and numerical evaluations" 192 : 243-260, 1999

      7 Huang YN, "Seismic Performance Assessment of Base-isolated Safety-related Nuclear Structures" 39 : 1421-1442, 2010

      8 American Society of Civil Engineers, "Seismic Design Criteria for Structures, Systems, and Components in Nuclear Facilities" ASCE

      9 American Society of Civil Engineers, "Seismic Analysis of Safety-Related Nuclear Structures and Commentry" ASCE 2000

      10 KEPCO Engineering & Construction Company, Inc, "SKN 3 & 4 Safety Related-Plant Manual-Main Stem System (MS), 9-521-M442-001"

      11 U.S Nuclear Regulatory Commission, "Regulatory Guide. 1.60, Design Response Spectra for Seismic Design of Nuclear Power Plants"

      12 KHNP, "Probabilistic Safety Assessment of Uljin No. 5 and No. 6"

      13 Electric Power Research Institute, "Piping and Fitting Dynamic Reliability Program"

      14 Choi IK, "Inelastic Energy Absorption Factor for the Seismic Probabilistic Risk Assessment of NPP Containment Structure" 5 (5): 47-56, 2001

      15 Ju BS, "Framework for Fragility Evaluation of Piping System" 2013

      16 Zhang T, "Analysis of JNES Seismic Tests on Degraded Piping"

      17 Hancock J, "An improved method of matching response spectra of recorded earthquake ground motion using wavelets" 10 (10): 67-89, 2006

      18 American Society of Mechanical Engineers, "ASME Boiler & Pressure Vessel Code"

      19 Gye MS, "A Research of Elbow Wall Thickness Effect in Nuclear Power Plant Piping System" Pusan National University 2013

      20 Xu, J, "A NRC-BNL benchmark evaluation of seismic analysis methods for non-classically damped coupled systems" 228 : 345-366, 2004

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      2027 평가예정 재인증평가 신청대상 (재인증)
      2021-01-01 평가 등재학술지 유지 (재인증) KCI등재
      2018-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2015-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2011-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2009-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2007-01-01 평가 등재 1차 FAIL (등재유지) KCI등재
      2005-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2002-01-01 평가 등재학술지 선정 (등재후보2차) KCI등재
      1999-01-01 평가 등재후보학술지 선정 (신규평가) KCI등재후보
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      기준연도 WOS-KCI 통합IF(2년) KCIF(2년) KCIF(3년)
      2016 0.48 0.48 0.44
      KCIF(4년) KCIF(5년) 중심성지수(3년) 즉시성지수
      0.39 0.35 0.664 0.17
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