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    Examination of the Coping Strategies (FLEX) of APR1400 for Extended Station Blackout using MARS Code

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    https://www.riss.kr/link?id=A104500877

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    Since the Fukushima Dai-ichi NPP accident, the Korean regulatory agency as well as the US NRC have strengthened the SBO mitigation capability for all operating and new reactors as a part of the defense-in-depth measure. In this paper, the multi-dimensional analysis of reactor safety (MARS) code is used to model APR1400 under the extended SBO condition. A thermal hydraulic analysis is undertaken to ascertain the plant's coping capability for up to 72 hours if a set of diverse and flexible coping strategies (FLEX) is implemented as proposed by the American nuclear energy institute, NEI[1]. Notably, for the extended SBO, the RCP seal leakage is an important yet uncertain parameter that may significantly affect the thermal hydraulic response of the plant. Given the significance and uncertainty of the RCP seal leakage rates on the plant's response, a parametric study is conducted for different leakage rates. The plant's response to the extended SBO with attendant RCP seal leakage solely relying on the existing equipment is first examined. Subsequently, an optimized coping strategy using the additional FLEX equipment (primary-side and secondary-side external injection) is developed with different RCP seal leakage rates for up to 72 hours into the accident.
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    Since the Fukushima Dai-ichi NPP accident, the Korean regulatory agency as well as the US NRC have strengthened the SBO mitigation capability for all operating and new reactors as a part of the defense-in-depth measure. In this paper, the multi-dimens...

    Since the Fukushima Dai-ichi NPP accident, the Korean regulatory agency as well as the US NRC have strengthened the SBO mitigation capability for all operating and new reactors as a part of the defense-in-depth measure. In this paper, the multi-dimensional analysis of reactor safety (MARS) code is used to model APR1400 under the extended SBO condition. A thermal hydraulic analysis is undertaken to ascertain the plant's coping capability for up to 72 hours if a set of diverse and flexible coping strategies (FLEX) is implemented as proposed by the American nuclear energy institute, NEI[1]. Notably, for the extended SBO, the RCP seal leakage is an important yet uncertain parameter that may significantly affect the thermal hydraulic response of the plant. Given the significance and uncertainty of the RCP seal leakage rates on the plant's response, a parametric study is conducted for different leakage rates. The plant's response to the extended SBO with attendant RCP seal leakage solely relying on the existing equipment is first examined. Subsequently, an optimized coping strategy using the additional FLEX equipment (primary-side and secondary-side external injection) is developed with different RCP seal leakage rates for up to 72 hours into the accident.

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    참고문헌 (Reference)

    1 U.S. NRC, "Recommendations for Enhancing Reactor Safety in the 21st Ceontury"

    2 Westinghouse, "Reactor Coolant Pump Seal Leakage Model for Westinghouse PWRs"

    3 TEPCO, "Overview of the Earthquake &Tsunami and Nuclear Accident: The Great East Japan Earthquake and Current Status of Nuclear Power Stations" 2011

    4 KAERI, "MARS code manual"

    5 Lee, S.W, "Extended Station Blackout Coping Capabilities of APR1400" 2014 : 2014

    6 Kim, W.B, "Extended Station Blackout Analyses of an APR1400with MARS-KS" 31 (31): 318-326, 2016

    7 Eom, S, "Examination of SBO Emergency Operating Procedure of APR1400 using MARS code" 2017

    8 NEI, "Diverse and Flexible Coping Strategies (FLEX) Implementation Guide, Rev.4"

    9 Hwang, J.R, "Developing Optimal Procedure of Emergency Outside Cooling Water Injection for APR1400 Extended SBO Scenario Using MARS Code" 2013

    10 KEPCO, "APR1400 Design Control Document Tier 2"

    1 U.S. NRC, "Recommendations for Enhancing Reactor Safety in the 21st Ceontury"

    2 Westinghouse, "Reactor Coolant Pump Seal Leakage Model for Westinghouse PWRs"

    3 TEPCO, "Overview of the Earthquake &Tsunami and Nuclear Accident: The Great East Japan Earthquake and Current Status of Nuclear Power Stations" 2011

    4 KAERI, "MARS code manual"

    5 Lee, S.W, "Extended Station Blackout Coping Capabilities of APR1400" 2014 : 2014

    6 Kim, W.B, "Extended Station Blackout Analyses of an APR1400with MARS-KS" 31 (31): 318-326, 2016

    7 Eom, S, "Examination of SBO Emergency Operating Procedure of APR1400 using MARS code" 2017

    8 NEI, "Diverse and Flexible Coping Strategies (FLEX) Implementation Guide, Rev.4"

    9 Hwang, J.R, "Developing Optimal Procedure of Emergency Outside Cooling Water Injection for APR1400 Extended SBO Scenario Using MARS Code" 2013

    10 KEPCO, "APR1400 Design Control Document Tier 2"

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    학술지 이력

    학술지 이력
    연월일 이력구분 이력상세 등재구분
    2027 평가 재인증평가 신청대상 (재인증)
    2021-01-01 등재 등재학술지 유지 (재인증) KCI등재
    2018-01-01 등재 등재학술지 유지 (등재유지) KCI등재
    2015-01-01 등재 등재학술지 유지 (등재유지) KCI등재
    2011-01-01 등재 등재 1차 FAIL (등재유지) KCI등재
    2009-01-01 등재 등재학술지 유지 (등재유지) KCI등재
    2006-01-01 등재 등재학술지 선정 (등재후보2차) KCI등재
    2005-06-16 학술지명변경 외국어명 : Jpurnal of Computatuonal Fluids Engineering -> Korean Society of Computatuonal Fluids Engineering KCI등재후보
    2005-01-01 등재 등재후보 1차 PASS (등재후보1차) KCI등재후보
    2004-01-01 등재 등재후보 1차 FAIL (등재후보1차) KCI등재후보
    2002-07-01 등재 등재후보학술지 선정 (신규평가) KCI등재후보
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    학술지 인용정보

    학술지 인용정보
    기준연도 WOS-KCI 통합IF(2년) KCIF(2년) KCIF(3년)
    2016 0.2 0.2 0.19
    KCIF(4년) KCIF(5년) 중심성지수(3년) 즉시성지수
    0.16 0.15 0.405 0.05
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