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      KCI등재 SCIE SCOPUS

      Development of the Digitalized Automatic Seismic Trip System for Nuclear Power Plants Using the Systems Engineering Approach

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      https://www.riss.kr/link?id=A104141127

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      다국어 초록 (Multilingual Abstract)

      The automatic seismic trip system (ASTS) continuously monitors PGA (peak ground acceleration) from the seismic wave,and automatically generates a trip signal. This work presents how the system can be designed by using a systems engineeringapproach und...

      The automatic seismic trip system (ASTS) continuously monitors PGA (peak ground acceleration) from the seismic wave,and automatically generates a trip signal. This work presents how the system can be designed by using a systems engineeringapproach under the given regulatory criteria. Overall design stages, from the needs analysis to design verification, have beenexecuted under the defined processes and activities. Moreover, this work contributes two significant design areas fordigitalized ASTS. These are firstly, how to categorize the ASTS if the ASTS has a backed up function of the manual reactortrip, and secondly, how to set the requirements using the given design practices either in overseas ASTS design or similardesign. In addition, the methodology for determining the setpoint can be applied to the I&C design and development projectwhich needs to justify the error sources correctly. The systematic approach that has been developed and realized in this workcan be utilized in designing new I&C (instrument and control system) as well.

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      참고문헌 (Reference)

      1 USNRC, "USNRC Reg. Guide 1.60, Design Response Spectra for Seismic Design of Nuclear Power Plants"

      2 USNRC, "USNRC Reg. Guide 1.29, Seismic Design Classification"

      3 R. Whorton, "US utility perspectives on earthquake response and seismic instrumentation" 1995

      4 R. Whorton, "US utility perspectives on earthquake response and seismic instrumentation" 1995

      5 MITI, "Technical Standards for Nuclear Power Plant Facilities"

      6 JEAG, "Technical Guidelines for Aseismic Design of Nuclear Power Plants"

      7 IEC, "Systems and software engineering -System life cycle processes"

      8 A. Kossiakoff, "System Engineering-Principles and Practice" Wiley

      9 "Standard Review Plan 3.7.1, Seismic Design Parameters" USNRC 2007

      10 IAEA, "Seismic Safety of Existing NPPs" IAEA 2009

      1 USNRC, "USNRC Reg. Guide 1.60, Design Response Spectra for Seismic Design of Nuclear Power Plants"

      2 USNRC, "USNRC Reg. Guide 1.29, Seismic Design Classification"

      3 R. Whorton, "US utility perspectives on earthquake response and seismic instrumentation" 1995

      4 R. Whorton, "US utility perspectives on earthquake response and seismic instrumentation" 1995

      5 MITI, "Technical Standards for Nuclear Power Plant Facilities"

      6 JEAG, "Technical Guidelines for Aseismic Design of Nuclear Power Plants"

      7 IEC, "Systems and software engineering -System life cycle processes"

      8 A. Kossiakoff, "System Engineering-Principles and Practice" Wiley

      9 "Standard Review Plan 3.7.1, Seismic Design Parameters" USNRC 2007

      10 IAEA, "Seismic Safety of Existing NPPs" IAEA 2009

      11 IAEA, "Seismic Safety of Existing NPPs" IAEA 2009

      12 GeoSIG Ltd, "Seismic Monitoring System-Acceptance criteria"

      13 KINS, "Safety Classification for PWR I&C system"

      14 IEEE, "IEEE standard for Software Verification and Validation"

      15 B.P. Allmann, "Global variations of stress drop for moderate to large earthquakes" 114 : 2009

      16 "Earthquake Preparedness and Responses for NPPs" IAEA 2011

      17 "Earthquake Instrumentation Criteria for Nuclear Power Plants"

      18 G. H Youn, "Development Status of Ground-motion Criteria for Operation of NPPs Amplification" 2009

      19 Ting Chow, "ASTS consulting report for Korea Power Engineering Company" INER. TW 2011

      20 "A Criterion for Determining Exceedance of the Operating Basis Earthquake" EPRI 1988

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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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