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      APR1400 원자로 내부구조물 종합진동평가프로그램용 측정센서 검토

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      https://www.riss.kr/link?id=A100173487

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      다국어 초록 (Multilingual Abstract)

      Reactor vessel internals comprehensive vibration assessment program(RVI CVAP) is one of the necessary tests to ensure the safety of nuclear power plants. RVI CVAP of U.S. nuclear regulatory commission regulatory guide 1.20(U.S. NRC R.G. 1.20) consists...

      Reactor vessel internals comprehensive vibration assessment program(RVI CVAP) is one of the necessary tests to ensure the safety of nuclear power plants. RVI CVAP of U.S. nuclear regulatory commission regulatory guide 1.20(U.S. NRC R.G. 1.20) consists of the analysis, measurement and inspection. One of the core technologies of the measurement program for RVI CVAP is to select suitable sensors because the measurement is conducted during the critical path of the construction period of nuclear power plants. Therefore, we analyzed RVI thermal-hydraulic and structure design data of Palo Verde nuclear power plant(U.S.), Yonggwang nuclear power plant(Korea) and APR1400 and researched measuring sensors used in them; moreover, we investigated sensors used for measurement of RVI CVAP for the last 20 years throughout the world. Based on these results, we selected suitable measuring sensors for RVI CVAP in advanced power reactor 1400(APR1400).

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      참고문헌 (Reference)

      1 Ko, D. Y., "Vibration Measurement Plan of RVI CVAP for Shin-kori Unit 4" Korean Nuclear Society Spring Meeting 1037-1038, 2009

      2 Korea Institute of Nuclear Safety, "Technical Review Report of Reactor Vessel Internals Comprehensive Vibration Assessment Program for Yonggwang Nuclear Power Station Unit 4" 1995

      3 Kepco Engineering and Construction Company Inc., "System Description for Reactor Internals Assembly" 2008

      4 Korea Electric Power Corp., "Special Test Part, Collection of Experience Record for Preoperational and Initial Startup Testing for Yonggwang Generating Station Unit 3, 4" 1995

      5 Korea Electric Power Corp., "Report on the Observation and Synthesis about CVAP in KNGR RVI" 2000

      6 U. S. Nuclear Regulatory Committee, "Regulatory Guide 1.20, Comprehensive Vibration Assessment Program for Reactor Internals during Preoperational and Initial Startup Testing, Rev. 3" 2007

      7 Jung, S. H., "Reactor Vessel Internals Comprehensive Vibration Assessment Program for Korea Standard Nuclear Power Plant" 15 (15): 7-14, 2005

      8 Kepco Engineering and Construction Company Inc., "Reactor Vessel Core Support and Internal Structures System Design Requirements" 2008

      9 Ko, D. Y., "Preliminary Determination of Measurement Sensors and Location for RVI CVAP of Shin-kori #4" 216-217, 2009

      10 Kim, K. H., "Hydraulic and Structural Analysis Methodology of RVI CVAP in Shin-kori 4" Korean Nuclear Society Spring Meeting 1113-1114, 2009

      1 Ko, D. Y., "Vibration Measurement Plan of RVI CVAP for Shin-kori Unit 4" Korean Nuclear Society Spring Meeting 1037-1038, 2009

      2 Korea Institute of Nuclear Safety, "Technical Review Report of Reactor Vessel Internals Comprehensive Vibration Assessment Program for Yonggwang Nuclear Power Station Unit 4" 1995

      3 Kepco Engineering and Construction Company Inc., "System Description for Reactor Internals Assembly" 2008

      4 Korea Electric Power Corp., "Special Test Part, Collection of Experience Record for Preoperational and Initial Startup Testing for Yonggwang Generating Station Unit 3, 4" 1995

      5 Korea Electric Power Corp., "Report on the Observation and Synthesis about CVAP in KNGR RVI" 2000

      6 U. S. Nuclear Regulatory Committee, "Regulatory Guide 1.20, Comprehensive Vibration Assessment Program for Reactor Internals during Preoperational and Initial Startup Testing, Rev. 3" 2007

      7 Jung, S. H., "Reactor Vessel Internals Comprehensive Vibration Assessment Program for Korea Standard Nuclear Power Plant" 15 (15): 7-14, 2005

      8 Kepco Engineering and Construction Company Inc., "Reactor Vessel Core Support and Internal Structures System Design Requirements" 2008

      9 Ko, D. Y., "Preliminary Determination of Measurement Sensors and Location for RVI CVAP of Shin-kori #4" 216-217, 2009

      10 Kim, K. H., "Hydraulic and Structural Analysis Methodology of RVI CVAP in Shin-kori 4" Korean Nuclear Society Spring Meeting 1113-1114, 2009

      11 Kepco Engineering and Construction Company Inc., "Fluid System and Component Engineering Design Data for Plant Safety, Containment and Performance Analyses" 2008

      12 Kepco Engineering and Construction Company Inc., "Design Specification for Reactor Vessel Core Support and Internal Structures" 2008

      13 Kepco Engineering and Construction Company Inc., "Design Data for The Hydraulic Loads on Reactor Internals During Normal Operation" 2008

      14 Korea Hydro and Nuclear Power Co., "Advanced Power Reactor 1400 Standard Safety Analysis Report" 2001

      15 Combustion Engineering Inc., "A Comprehensive Vibration Assessment Program for the Prototype System 80 Reactor Internals Palo Verde Nuclear Generating Station Unit 1" 1984

      16 Korea Heavy Industry Co., "A Comprehensive Vibration Assessment Program for Yonggwang Nuclear Generating Station Unit 4, Final Evaluation of Pre-Core Hot Functional Measurement and Inspection Program" 1995

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      학술지 이력

      학술지 이력
      연월일 이력구분 이력상세 등재구분
      2026 평가예정 재인증평가 신청대상 (재인증)
      2020-01-01 평가 등재학술지 유지 (재인증) KCI등재
      2017-01-01 평가 등재학술지 유지 (계속평가) KCI등재
      2013-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2010-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2009-02-05 학회명변경 영문명 : Korean Society For Noise And Vibration Engeering (Ksnve) -> Korean Society for Noise and Vibration Engineering(KSNVE) KCI등재
      2008-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2006-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2004-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2001-07-01 평가 등재학술지 선정 (등재후보2차) KCI등재
      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 0.28 0.28 0.26
      KCIF(4년) KCIF(5년) 중심성지수(3년) 즉시성지수
      0.25 0.23 0.457 0.05
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