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      KCI등재 SCIE SCOPUS

      Shaking table test and numerical analysis of nuclear piping under low- and high-frequency earthquake motions

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      https://www.riss.kr/link?id=A108236368

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      다국어 초록 (Multilingual Abstract)

      A nuclear power plant (NPP) piping is designed against low-frequency earthquakes. However, earthquakes that can occur at NPP sites in the eastern part of the United States, northern Europe, and Korea are high-frequency earthquakes. Therefore, this stu...

      A nuclear power plant (NPP) piping is designed against low-frequency earthquakes. However, earthquakes that can occur at NPP sites in the eastern part of the United States, northern Europe, and Korea are high-frequency earthquakes. Therefore, this study conducts bi-directional shaking table tests on actualscale NPP piping and studies the response characteristics of low- and high-frequency earthquake motions. Such response characteristics are analyzed by comparing several responses that occur in the piping. Also, based on the test results, a piping numerical analysis model is developed and validated. The piping seismic performance under high-frequency earthquakes is derived. Consequently, the highfrequency excitation caused a large amplification in the measured peak acceleration responses compared to the low-frequency excitation. Conversely, concerning relative displacements, strains, and normal stresses, low-frequency excitation responses were larger than high-frequency excitation responses. Main peak relative displacements and peak normal stresses were 60%e69% and 24%e49% smaller in the high-frequency earthquake response than the low-frequency earthquake response. This phenomenon was noticeable when the earthquake motion intensity was large. The piping numerical model simulated the main natural frequencies and relative displacement responses well. Finally, for the stress limit state, the seismic performance for high-frequency earthquakes was about 2.7 times greater than for low-frequency earthquakes

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      참고문헌 (Reference)

      1 이현미 ; 김민규 ; 신동훈 ; 최인길, "국내 주요 광역 도시에 대한 등재해도 스펙트럼 분석" 한국지진공학회 17 (17): 71-77, 2013

      2 임승현 ; 최인길, "구조물 및 기기의 한계성능 평가를 위한 고진동수 지진특성을 반영한 응답스펙트럼 형상" 한국지진공학회 24 (24): 1-8, 2020

      3 박효상 ; Duy-Duan Nguyen ; 이태형, "고주파 지진이 원자력 발전소 설비의 동적거동에 미치는 영향" 한국방재학회 17 (17): 285-294, 2017

      4 J. Lockau, "The influence of high-frequency excitation on piping and support design" 106 (106): 177-187, 1984

      5 A. Gupta, "Significance of non-classical damping in seismic qualification of equipment and piping" 317 : 90-99, 2017

      6 S. Singh, "Seismic response of electrical equipment subjected to highefrequency ground motions" 374 : 111046-, 2021

      7 H. Son, "Seismic qualification of electrical cabinet using high-fidelity simulation under high frequency earthquakes" 12 (12): 8048-, 2020

      8 USNRC, "Seismic System Analysis. Standard Review Plan, NUREG-0800, Rev. 3" U.S. Nuclear Regulatory Commission 2007

      9 EPRI, "Seismic Probabilistic Risk Assessment Implementation Guide" Electric Power Research Institute 2013

      10 C. Rydell, "Seismic High-Frequency Content Loads on Structures and Components within Nuclear Facilities" KTH Royal Institute of Technology 2014

      1 이현미 ; 김민규 ; 신동훈 ; 최인길, "국내 주요 광역 도시에 대한 등재해도 스펙트럼 분석" 한국지진공학회 17 (17): 71-77, 2013

      2 임승현 ; 최인길, "구조물 및 기기의 한계성능 평가를 위한 고진동수 지진특성을 반영한 응답스펙트럼 형상" 한국지진공학회 24 (24): 1-8, 2020

      3 박효상 ; Duy-Duan Nguyen ; 이태형, "고주파 지진이 원자력 발전소 설비의 동적거동에 미치는 영향" 한국방재학회 17 (17): 285-294, 2017

      4 J. Lockau, "The influence of high-frequency excitation on piping and support design" 106 (106): 177-187, 1984

      5 A. Gupta, "Significance of non-classical damping in seismic qualification of equipment and piping" 317 : 90-99, 2017

      6 S. Singh, "Seismic response of electrical equipment subjected to highefrequency ground motions" 374 : 111046-, 2021

      7 H. Son, "Seismic qualification of electrical cabinet using high-fidelity simulation under high frequency earthquakes" 12 (12): 8048-, 2020

      8 USNRC, "Seismic System Analysis. Standard Review Plan, NUREG-0800, Rev. 3" U.S. Nuclear Regulatory Commission 2007

      9 EPRI, "Seismic Probabilistic Risk Assessment Implementation Guide" Electric Power Research Institute 2013

      10 C. Rydell, "Seismic High-Frequency Content Loads on Structures and Components within Nuclear Facilities" KTH Royal Institute of Technology 2014

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

      12 ASME, "Rules for Construction of Nuclear Facility Components. ASME CODE Section III, Division I, Subsection NB" The American Society of Mechanical Engineers 2007

      13 In-KilChoi ; Young-SunChoun ; Jeong-MoonSeo, "Reevaluation of Seismic Fragility Parameters of Nuclear Power Plant Components Considering Uniform Hazard Spectrum" 한국원자력학회 34 (34): 586-595, 2002

      14 S. Kwag, "Probabilistic risk assessment framework for structural systems under multiple hazards using Bayesian statistics" 315 : 20-34, 2017

      15 S. Kwag, "Probabilistic risk assessment based model validation method using Bayesian network" 169 : 380-393, 2018

      16 C. Rydell, "Piping system subjected to seismic hard rock high frequencies" 278 : 302-309, 2014

      17 곽신영 ; 임승현 ; 곽진성 ; 이환호 ; 오진호 ; 구경회, "Mitigation of seismic responses of actual nuclear piping by a newly developed tuned mass damper device" 한국원자력학회 53 (53): 2728-2745, 2021

      18 K. Yoshida, "M6. 7 Yamagata-Oki earthquake in the stress shadow of 2011 Tohoku-Oki earthquake: was it caused by the reduction in fault strength?" 793 : 228609-, 2019

      19 J. P. Vayda, "Influence of gap size on the dynamic behaviour of piping systems" 67 (67): 145-164, 1982

      20 Y. S. Choun, "Improvement of the seismic safety of existing nuclear power plants by an increase of the component seismic capacity : a case study" 238 (238): 1410-1420, 2008

      21 A. G. Youtsos, "Impact of structural steel flexibility and restraints gaps on the dynamic behaviour of piping" 114 (114): 135-145, 1989

      22 A. G. Youtsos, "High frequency response evaluation of piping systems" 36 (36): 269-287, 1989

      23 EPRI, "High Frequency Program: High Frequency Testing Summary" Electric Power Research Institute (EPRI) 2014

      24 EPRI, "High Frequency Program: Application Guidance for Functional Confirmation and Fragility Evaluation" Electrical Power Research Institute 2015

      25 M. Baba, "Fukushima accident: what happened?" 55 : 17-21, 2013

      26 F. Steinwender, "Experimental investigation of the load transfer behaviour of piping supports under high-frequency excitation" 83 (83): 27-30, 1984

      27 KAERI, "Evaluation of High Frequency Ground Motion Effects on the Seismic Capacity of Nuclear Power Plant Equipment" Korean Atomic Energy Research Institute 2003

      28 S. Kwag, "Efficient seismic fragility analysis for large-scale piping system utilizing Bayesian approach" 10 (10): 1515-, 2020

      29 전법규 ; 손호영 ; 임승현 ; 최인길 ; 주부석, "Dynamic characteristics of single door electrical cabinet under rocking: Source reconciliation of experimental and numerical findings" 한국원자력학회 53 (53): 2387-2395, 2021

      30 I. K. Choi, "Development of the site-specific uniform hazard spectra for Korean nuclear power plant sites" 239 (239): 790-799, 2009

      31 USNRC, "Development of floor design response spectra for seismic design of floor-supported equipment or components"

      32 S. Kwag, "Development of efficient complete-sampling-based seismic PSA method for nuclear power plant" 197 : 106824-, 2020

      33 R. Morita, "Development and analysis of seismic experience database of structures, systems and components in nuclear power plants based on investigation reports and maintenance records" 375 : 111078-, 2021

      34 USNRC, "Design Response Spectra for Seismic Design of Nuclear Power Plants. Regulatory Guide 1.60, Rev. 2" Nuclear Regulatory Commission 2014

      35 EPRI, "Considerations for NPP Equipment and Structures Subjected to Response Levels Caused by High Frequency Ground Motions" Electrical Power Research Institute 2007

      36 S. Kwag, "Computationally efficient fragility assessment using equivalent elastic limit state and Bayesian updating" 197 : 1-11, 2018

      37 EPRI, "Advanced Nuclear Technology: High-Frequency Seismic Loading Evaluation for Standard Nuclear Power Plants" Electrical Power Research Institute 2017

      38 M. K. Kim, "A shaking table test for an evaluation of seismic behavior of 480 V MCC" 243 : 341-355, 2012

      39 USNRC, "A Performance-Based Approach to Define the Site-specific Earthquake Ground Motion. Regulatory Guide 1.208" U.S. Nuclear Regulatory Commission 2007

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      학술지 이력

      학술지 이력
      연월일 이력구분 이력상세 등재구분
      2023 평가예정 해외DB학술지평가 신청대상 (해외등재 학술지 평가)
      2020-01-01 평가 등재학술지 유지 (해외등재 학술지 평가) KCI등재
      2014-01-01 평가 SCIE 등재 (등재유지) KCI등재
      2014-01-01 평가 SCOPUS 등재 (등재유지) KCI등재
      2011-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2009-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2007-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2006-07-31 학술지명변경 한글명 : Jorunal of the Korean Nuclear Society -> Nuclear Engineering and Technology
      외국어명 : 미등록 -> Nuclear Engineering and Technology
      KCI등재후보
      2004-01-01 평가 등재후보학술지 선정 (신규평가) KCI등재후보
      2003-01-01 평가 등재후보 1차 PASS (등재후보1차) KCI등재후보
      2002-01-01 평가 등재후보학술지 유지 (등재후보1차) KCI등재후보
      1999-01-01 평가 등재후보학술지 선정 (신규평가) KCI등재후보
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      학술지 인용정보

      학술지 인용정보
      기준연도 WOS-KCI 통합IF(2년) KCIF(2년) KCIF(3년)
      2016 1.04 0.17 0.77
      KCIF(4년) KCIF(5년) 중심성지수(3년) 즉시성지수
      0.63 0.56 0.343 0.11
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