한국지진공학회논문집 (Journal of the Earthquake Engineering Society of Korea)

  • 제28권6호
  • /
  • Pages.335-344
  • /
  • 2024
  • /
  • 1226-525X(pISSN)
  • /
  • 2234-1099(eISSN)
한국지진공학회 (Earthquake Engineering Society of Korea)
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원전 지진 리스크 저감을 위한 MACST 설비의 내진 성능 최적화

Identification of Optimal Seismic Capacity of MACST Facilities for Seismic Risk Reduction of Nuclear Power Plant

  • 김민규 (한국원자력연구원 구조.지진안전연구부) ;
  • 최유정 (한국원자력연구원 구조.지진안전연구부) ;
  • 장승현 (한국원자력연구원 구조.지진안전연구부) ;
  • 함대기 (한국원자력연구원 구조.지진안전연구부)
  • Kim, Minkyu (Structural and Seismic Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Choi, Eujeong (Structural and Seismic Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Jang, Seunghyun (Structural and Seismic Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Hahm, Daegi (Structural and Seismic Safety Research Division, Korea Atomic Energy Research Institute)
  • 투고 : 2024.08.02
  • 심사 : 2024.09.30
  • 발행 : 2024.11.01
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초록

This study investigates the risk reduction effect and identifies the optimal capacity of Multi-barrier Accident Coping Strategy (MACST) facilities for nuclear power plants (NPPs) under seismic hazard. The efficacy of MACST facilities in OPR1000 and APR1400 NPP systems is evaluated by utilizing the Improved Direct Quantification of Fault Tree with Monte Carlo Simulation (I-DQFM) method. The analysis encompasses a parametric study of the seismic capacity of two MACST facilities: the 1.0 MW large-capacity mobile generator and the mobile low-pressure pump. The results demonstrate that the optimal seismic capacity of MACST facilities for both NPP systems is 1.5g, which markedly reduces the probability of core damage. In particular, the core damage risk is reduced by approximately 23% for the OPR1000 system, with the core damage fragility reduced by approximately 72% at 1.0g seismic intensity. For the APR1400 system, the implementation of MACST is observed to reduce the core damage risk by approximately 17% and the core damage fragility by approximately 44% under the same conditions. These results emphasize the significance of integrating MACST facilities to enhance the resilience and safety of NPPs against seismic hazard scenarios, highlighting the necessity for continuous adaptation of safety strategies to address evolving natural threats.

키워드

과제정보

본 연구는 2022년도 정부(과학기술정보통신부)의 재원으로 한국연구재단의 지원을 받아 수행된 연구임(No. RS-2022-00154571).

참고문헌

  1. Nuclear Energy Institute (NEI). NEI 12-06 Rev 2 Diverse and Flexible Coping Strategies (FLEX) Implementation Guide. 2015 Dec.
  2. Suh YA, Kim J, Hwang MJ. Sensitivity Analysis via Modelling FLEX/MACST Equipment into a PSA Model. Trans Korean Nucl Soc Virtual Autumn Meeting. 2020 Dec.
  3. Song J, Kim S, Kim J, Chu B, Kim CH. Preliminary assessment of coping capacity of HANUL unit 3 under ELAP and LUHS. Trans Korean Nucl Soc Spring Meeting; 2018 May 17-18; Jeju, Korea; c2018. 3 p.
  4. Park Y, Kim S, Jin Y, Kim DH, Jae M. Evaluation for Accident Mitigation Effect of External Injection at WH600 using MELCOR. Trans Korean Nucl Soc Virtual Autumn Meeting. 2020 Dec.
  5. Lee H, Choi W, Kim SJ. Sensitivity Analysis at the Time of MACST Action in Severe Accidents caused by Station Black Out (SBO). Trans Korean Nucl Soc Virtual Spring Meeting. 2020 Jul.
  6. Kim IS, Kim BG, Choi DI, Lee EC. Incorporating MACST Mitigation Strategies into PSA Models: HRA and Data Issues. Trans Korean Nucl Soc Autumn Meeting. 2017 Oct.
  7. Shin H, Jae M. Analysis of External Injection Effects for Low-Pressure Mobile Pumps using MELCOR Code. Trans Korean Nucl Soc Virtual Spring Meeting. 2021 May.
  8. Yun DJ, Hong CS, Lee SC, Kim SM, Ha SJ. Validation Plan of Emergency Operating Guideline for Continuous Multiple Failure Accident in OPR1000 Nuclear Power Plants. Trans Korean Nucl Soc Autumn Meeting. 2018 Oct.
  9. Yoon JY, Lim HG, Park JW, Kang SW. MUPSA-based evaluation of portable equipment utilization for risk reduction in nuclear power plants: framework and case study. Nucl Eng Technol. 2024 Jun;56(11):4587-4600. DOI:0.1016/j.net.2024.06.021 https://doi.org/10.1016/j.net.2024.06.021
  10. Kwag S, Ha JG, Kim MK, Kim JH. Development of efficient external multi-hazard risk quantification methodology for nuclear facilities. Energies. 2019;12(20):3925.
  11. Kwag S, Hahm D. Development of an earthquake-induced landslide risk assessment approach for nuclear power plants. Nucl Eng Technol. 2018 Dec;50(8):1372-1386.
  12. Reed JW, Kennedy RP. Methodology for Developing Seismic Fragilities. Final Report TR-103959. 1994; Palo Alto, CA. Electric Power Research Institute.
  13. Eb isawa K, Abe K, Muramatsu K, Itoh M, Kohno K, Tanaka T. Evaluation of response factors for seismic probabilistic safety assessment of nuclear power plants. Nucl Eng Des. 1994;147(2): 197-210.
  14. Watanabe Y, Oikawa T, Muramatsu K. Development of the DQFM method to consider the effect of correlation of component failures in seismic PSA of nuclear power plant. Reliab Eng Syst Saf. 2003; 79(3):265-279.
  15. Ellingwood B. Validation studies of seismic PRAs. Nucl Eng Des. 1990;123(2-3):189-196.
  16. Eem S, Choi IK, Cha SL, Kwag S. Seismic response correlation coefficient for the structures, systems and components of the Korean nuclear power plant for seismic prob ab ilistic safety assessment. Ann Nucl Energy. 2021;150:107759.