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      KCI등재 SCIE SCOPUS

      Effect of slab stiffness on floor response spectrum and fragility of equipment in nuclear power plant building

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      https://www.riss.kr/link?id=A108816737

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      다국어 초록 (Multilingual Abstract)

      The floor response spectrum (FRS) is used to evaluate the seismic demand of equipment installed in nuclear power plants. In the conventional design practice of NPP structure, the FRS is simplified using the lumped-mass stick model (LMSM), assuming the floor slab as a rigid diaphragm. In the present study, to study the variation of seismic response in a floor, the FRSs at different locations were generated by 3-D finite element model, and the response was compared to that of the rigid diaphragm model. The result showed that the FRS significantly varied due to the large opening in a floor, which was not captured by the rigid diaphragm model. Based on the result, seismic fragility analysis was performed for the anchorage of a heat exchanger, to investigate the effect of location-dependent FRS disparity on the high confidence low probability of failure (HCLPF).
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      The floor response spectrum (FRS) is used to evaluate the seismic demand of equipment installed in nuclear power plants. In the conventional design practice of NPP structure, the FRS is simplified using the lumped-mass stick model (LMSM), assuming the...

      The floor response spectrum (FRS) is used to evaluate the seismic demand of equipment installed in nuclear power plants. In the conventional design practice of NPP structure, the FRS is simplified using the lumped-mass stick model (LMSM), assuming the floor slab as a rigid diaphragm. In the present study, to study the variation of seismic response in a floor, the FRSs at different locations were generated by 3-D finite element model, and the response was compared to that of the rigid diaphragm model. The result showed that the FRS significantly varied due to the large opening in a floor, which was not captured by the rigid diaphragm model. Based on the result, seismic fragility analysis was performed for the anchorage of a heat exchanger, to investigate the effect of location-dependent FRS disparity on the high confidence low probability of failure (HCLPF).

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      참고문헌 (Reference)

      1 김민규 ; 최인길, "원전 전기캐비넷의 지진취약도 재평가를 위한 진동대 실험" 한국전산구조공학회 24 (24): 295-306, 2011

      2 최인길, "설계초과 지진에 대한 원전 지진안전성 평가기술 고찰 및 제언" 한국압력기기공학회 13 (13): 1-15, 2017

      3 B.B. Torkian, "Validation of lumped mass stick models for surface founded structures" 2013

      4 A.R. Kottke, "Technical Manual for Strata" Pacific Earthquake Engineering Research Center, University of California 2008

      5 U.S. NRC, "Technical Basis for Revision of Regulatory Guidance on Design Grond Motions: Hazard-and Risk-Consistent Ground Motion Spectra Guidelines" U.S. Nuclear Regulatory Commission 2001

      6 KEPCO, "Status Report - APR1400 (KEPCO E&C/KHNP)" Korea Electric Power Corporation & Korea Hydro & Nuclear Power Co., Ltd. 2020

      7 U.S. NRC, "Standard Review Plan, Revision 4" Nuclear Regulatory Commission 2014

      8 V. Varma, "Simplified approach for seismic analysis of structures" 2 (2): 207-225, 2002

      9 NIST, "Selecting and Scaling Earthquake Ground Motions for Performing Response-History Analyses" National Institute of Standards and Technology 2011

      10 Y. -N. Huang, "Seismic performance assessment of baseisolated safety-related nuclear strucures" 39 (39): 1421-1442, 2010

      1 김민규 ; 최인길, "원전 전기캐비넷의 지진취약도 재평가를 위한 진동대 실험" 한국전산구조공학회 24 (24): 295-306, 2011

      2 최인길, "설계초과 지진에 대한 원전 지진안전성 평가기술 고찰 및 제언" 한국압력기기공학회 13 (13): 1-15, 2017

      3 B.B. Torkian, "Validation of lumped mass stick models for surface founded structures" 2013

      4 A.R. Kottke, "Technical Manual for Strata" Pacific Earthquake Engineering Research Center, University of California 2008

      5 U.S. NRC, "Technical Basis for Revision of Regulatory Guidance on Design Grond Motions: Hazard-and Risk-Consistent Ground Motion Spectra Guidelines" U.S. Nuclear Regulatory Commission 2001

      6 KEPCO, "Status Report - APR1400 (KEPCO E&C/KHNP)" Korea Electric Power Corporation & Korea Hydro & Nuclear Power Co., Ltd. 2020

      7 U.S. NRC, "Standard Review Plan, Revision 4" Nuclear Regulatory Commission 2014

      8 V. Varma, "Simplified approach for seismic analysis of structures" 2 (2): 207-225, 2002

      9 NIST, "Selecting and Scaling Earthquake Ground Motions for Performing Response-History Analyses" National Institute of Standards and Technology 2011

      10 Y. -N. Huang, "Seismic performance assessment of baseisolated safety-related nuclear strucures" 39 (39): 1421-1442, 2010

      11 S. Damolini, "Seismic SSI analysis comparison between detailed and discretized modeling of an auxiliary/control building" 2019

      12 S. El-Bahey, "Seismic SSI analysis comparison between detailed and discretized modeling of an auxiliary control building" 2017

      13 EPRI, "Seismic Fragility and Seismic Margin Guidance for Seismic Probabilistic Risk Assessments" Electric Power Research Institute 2018

      14 KEPCO, "Seismic Design Bases for the APR1400 Standard Plant Design" Korea Electric Power Corporation & Korea Hydro & Nuclear Power Co., Ltd. 2013

      15 ASCE, "Seismic Analysis of Safety-Related Nuclear Structures" American Society of Civil Engineers 2017

      16 R. P. Kennedy, "Probabilistic seismic safety study of an existing nuclear power plant" 59 (59): 315-338, 1980

      17 G. R. Toro, "Probabilistic Models of Site Velocity Profiles for Generic and Sitespecific Ground-Motion Amplification Studies" Brookhaven National Laboratory 1995

      18 Duy-Duan Nguyen ; Bidhek Thusa ; 한동석 ; 이태형, "Identifying signifi cant earthquake intensity measures for evaluating seismic damage and fragility of nuclear power plant structures" 한국원자력학회 52 (52): 192-205, 2020

      19 G. K. Kulak, "Guide to Design Criteria for Bolted and Riveted Joints" Wiley & Son 1987

      20 G. Hardy, "Finite element and lumped mass structure modelling for SPRAs" 2015

      21 KEPCO, "Finite Element Seismic Models for SSI Analyses of the NI Buildings of the APR1400 Standard Plant" Korea Electric Power Corporation &Korea Hydro & Nuclear Power Co., Ltd 2013

      22 이은행 ; 김재민 ; 주광호 ; 김현욱, "Evaluation of the Soil-structure Interaction Effect on Seismically Isolated Nuclear Power Plant Structures" 한국지진공학회 20 (20): 379-389, 2016

      23 M. B. Darendeli, "Development of a New Family of Normalized Modulus Reduction and Material Damping Curves" The University of Texas 2001

      24 U.S. NRC, "Development of Criteria for Seismic Review of Selected Nuclear Power Plants" U.S. Nuclear Regulatory Commission 1978

      25 H.H.M. Hwang, "Determination of HCLPF value for seismic margins study" 1989

      26 U.S. NRC, "Damping Values for Seismic Design of Nuclear Power Plants, Revision 1" U.S. Nuclear Regulatory Commission 2007

      27 R. Eligehausen, "Behavior of fasteners loaded in tension in cracked reinforced concrete" 92 (92): 365-379, 1995

      28 ANSYS, Inc., "Ansys® Mechanical, Release 20.2"

      29 R. Eligehausen, "Anchorage in Concrete Construction" Ernst &Sohn 2006

      30 "ACI Committee 349, Code Requirements for Nuclear Safety-Related Concrete Structures and Commentary" American Concrete Institute 2013

      31 "ACI Committee 318, Building Code Requirements for Structural Concrete" American Concrete Institute 318-319, 2019

      32 J.R. Nie, "A study of the effect of floor flexibility on building response using the KK NPP experience" 2013

      33 T. Radford, "A case study on the effect of detailed 3D finite element modelling on nuclear power plant building response" 2015

      34 MATLAB, "9.11.0.1809720 (R2021b)"

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