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다수기의 확률론적 지진안전성 평가를 위한 지진손상 상관계수의 적용

Feasibility Study of Seismic Probabilistic Risk Assessment for Multi-unit NPP with Seismic Failure Correlation

  • 임승현 (경북대학교 융복합시스템공학과 플랜트시스템전공) ;
  • 곽신영 (한밭대학교 건설환경공학과) ;
  • 최인길 (한국원자력연구원 첨단구조.지진안전연구부)
  • Eem, Seunghyun (Department of Convergence and Fusion System Engineering, Kyungpook National University) ;
  • Kwag, Shinyoung (Department of Civil & Environmental Engineering, Hanbat National University) ;
  • Choi, In-Kil (Advanced Structural and Seismic Safety Research Division, Korea Atomic Energy Research Institute)
  • 투고 : 2021.07.21
  • 심사 : 2021.08.30
  • 발행 : 2021.10.31

초록

후쿠시마 원전사고 발생으로 다수기의 지진안전성에 관한 연구의 필요성이 부각되었다. 한 부지에 건설된 원자력발전소의 경우 유사한 지진응답을 보이기 때문에 적게나마 원자력발전소 SSCs간의 지진손상에 대하여 상관성이 존재하므로 합리적 지진안전성 평가를 위하여 지진손상 상관성을 고려하여야 한다. 본 연구에서는 쌍둥이 호기의 필수전원상실사건에 대하여 확률론적 지진안전성 평가를 수행하였다. 적절한 지진손상 상관계수를 도출하기 위하여 확률론적 지진응답해석을 수행하여 적용하였다. External Event Mensuration System 프로그램을 활용하여 다수기의 필수전원상실사건의 고장수목을 구성하여 지진취약도 및 지진리스크를 분석하였다. 또한 SSCs간의 지진손상 상관성을 완전독립 및 완전종속으로 고려하여 비교 분석을 수행하였다.

The 2011 East Japan Earthquake caused accidents at a number of nuclear power plants in Fukushima, highlighting the need for a study on the seismic safety of multiple NPP (Nuclear Power Plant) units. In the case of nuclear power plants built on a site that shows a similar seismic response, there is at least a correlation between the seismic damage of structures, systems, and components (SSCs) of nuclear power plants. In this study, a probabilistic seismic safety assessment was performed for the loss of essential power events of twin units. To derive an appropriate seismic damage correlation coefficient, a probabilistic seismic response analysis was performed. Using the external event mensuration system program, we analyzed the seismic fragility and seismic risk by composing a failure tree of multiple loss of essential power events. Additionally, a comparative analysis was performed considering the seismic damage correlation between SSCs as completely independent and completely dependent.

키워드

과제정보

본 연구는 2020년도 한국연구재단의 지원을 받아 수행한 연구과제입니다(No. 2020R1G1A1007570).

참고문헌

  1. Choi, G.G., Jung, W.S., Park, S.K. (2021) Sensitivity Study on the Correlation Level of Seismic Failures in Seismic Probabilistic Safety Assessments, Energ., 14(10), 2955.
  2. Ebisawa, K., Abe, K., Muramatsu, K., Itoh, M., Kohno, K., Tanaka, T. (1994) Evaluation of Response Factors for Seismic Probabilistic Safety Assessment of Nuclear Power Plants, Nucl. Eng. & Des., 147(2), pp.197~210. https://doi.org/10.1016/0029-5493(94)90206-2
  3. Eem, S., Choi, I.K. (2019a) Influence Analysis of Seismic Risk due to the Failure Correlation in Seismic Probabilistic Safety Assessment, J. Earthq. Eng. Soc. Korea, 23(2), pp.101~108. https://doi.org/10.5000/EESK.2019.23.2.101
  4. Eem, S., Choi, I.K. (2019b) Influence in Seismic Fragility of Systems due to Seismic Correlation, In EESK spring workshop, c2019. pp.115~116.
  5. Eem, S., Kwag, S., Choi, I.K., Jeon, B.G., Park, D.U. (2021a) The Effects of Seismic Failure Correlaitons on the Probabilistic Seismic Safety Assessments of Nuclaer Power Plants, J. Earthq. Eng. Soc. Korea, 25(2), pp.53~58. https://doi.org/10.5000/EESK.2021.25.2.053
  6. Eem, S., Choi, I.K., Yang, B., Kwag, S. (2021b) Methodology of Seismic Response Correlation Coefficient Calculation for Seismic Probabilistic Safety Assessment of Multi-unit Nuclear Power Plants, Nucl. Eng. & Technol., 53(3), pp.967~973. https://doi.org/10.1016/j.net.2020.07.032
  7. Eem, S., Choi, I.K., Cha, S.L., Kwag, S. (2021c) Seismic Response Correlation Coefficient for the Structures, Systems and Components of the Korean Nuclear Power Plant for Seismic Probabilistic Safety Assessment, Ann. Nucl. Energy, 150, 107759. https://doi.org/10.1016/j.anucene.2020.107759
  8. Kwag, S., Choi, E., Eem, S., Ha, J.G., Hahm, D. (2021) Toward Improvement of Sampling-based Seismic Probabilistic Safety Assessment Method for Nuclear Facilities using Composite Distribution and Adaptive Discretization, Reliab. Eng. & Syst. Saf., 107809.
  9. Kwag, S., Eem, S., Park, J., Choi, I.K. (2020) Sampling-based Approach for Seismic Probabilistic Risk Assessment, J. Comput. Struct. Eng. Inst. Korea, 33(2), pp.129~136. https://doi.org/10.7734/COSEIK.2020.33.2.129
  10. Smith, P.D., Dong, R.G., Bernreuter, D.L., Bohn, M.P., Chuang, T.Y., Cummings, G.E., Smith, P.D., Dong, R.G., Bernreuter, D.L., Bohn, M.P., Chuang, T.Y., Cummings, G.E., Johnson, J.J., Mensing, R.W., Wells, J.E. (1981) Seismic Safety Margins Research Program, Phase I Final Report-Overview (No. NUREG/CR-2015 (VOL. 1)). Lawrence Livermore Laboratory, c1981.
  11. US Nuclear Regulatory Commission (1990) Procedures for the External Event Core Damage Frequency Analyses for NUREG-1150 (NUREG/ CR-4840). Washington, DC.
  12. US Nuclear Regulatory Commission (2014) Regulatory Guide 1.60: Design Response Spectra for Seismic Design of Nuclear Power Plants. c2014.