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구조물 및 기기의 내진성능 평가를 위한 고주파수 지진에 의한 원자력발전소의 지진응답 증폭계수

Seismic Response Amplification Factors of Nuclear Power Plants for Seismic Performance Evaluation of Structures and Equipment due to High-frequency Earthquakes

  • 임승현 (경북대학교 융복합시스템공학부 플랜트시스템전공) ;
  • 최인길 (한국원자력연구원 기계.구조안전연구부) ;
  • 전법규 (부산대학교 지진방재연구센터) ;
  • 곽신영 (한밭대학교 건설환경공학과)
  • Eem, Seung-Hyun (Major in Plant System Engineering, School of Convergence & Fusion System Engineering, Kyungpook National University) ;
  • Choi, In-Kil (Mechanical and Structural Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Jeon, Bub-Gyu (Seismic Research and Test Center, Pusan National University) ;
  • Kwag, Shinyoung (Department of Civil & Environmental Engineering, Hanbat National University)
  • 투고 : 2020.01.22
  • 심사 : 2020.02.27
  • 발행 : 2020.05.01

초록

Analysis of the 2016 Gyeongju earthquake and the 2017 Pohang earthquake showed the characteristics of a typical high-frequency earthquake with many high-frequency components, short time strong motion duration, and large peak ground acceleration relative to the magnitude of the earthquake. Domestic nuclear power plants were designed and evaluated based on NRC's Regulatory Guide 1.60 design response spectrum, which had a great deal of energy in the low-frequency range. Therefore, nuclear power plants should carry out seismic verification and seismic performance evaluation of systems, structures, and components by reflecting the domestic characteristics of earthquakes. In this study, high-frequency amplification factors that can be used for seismic verification and seismic performance evaluation of nuclear power plant systems, structures, and equipment were analyzed. In order to analyze the high-frequency amplification factor, five sets of seismic time history were generated, which were matched with the uniform hazard response spectrum to reflect the characteristics of domestic earthquake motion. The nuclear power plant was subjected to seismic analysis for the construction of the Korean standard nuclear power plant, OPR1000, which is a reactor building, an auxiliary building assembly, a component cooling water heat exchanger building, and an essential service water building. Based on the results of the seismic analysis, a high-frequency amplification factor was derived upon the calculation of the floor response spectrum of the important locations of nuclear power plants. The high-frequency amplification factor can be effectively used for the seismic verification and seismic performance evaluation of electric equipment which are sensitive to high-frequency earthquakes.

키워드

참고문헌

  1. Korea Meteorological Administration. Earthquake Notification - 2016. 9. 12. 20:37. Official notice. c2016.
  2. Eem SH, Choi IK. Shape of the Response Spectrum for Evaluation of the Ultimate Seismic Capacity of Structures and Equipment Including High-frequency Earthquake Characteristics. Journal of the Earthquake Engineering Society of Korea. 2019 Jan;24(1):1-8. https://doi.org/10.5000/EESK.2020.24.1.001
  3. Korea Meteorological Administration. Earthquake Notification - 2017. 11. 15. Official notice. c2017.
  4. Eem SH, Choi IK. Seismic Response Analysis of Nuclear Power Plant Structures and Equipment due to the Pohang Earthquake. Journal of the Earthquake Engineering Society of Korea. 2018 Apr;22(3): 113-119. https://doi.org/10.5000/EESK.2018.22.3.113
  5. Eem SH, Yang BJ, Jeon HM. Earthquake Damage Assessment of Buildings Using Opendata in the Pohang and the Gyeongju Earthquakes. Journal of the Earthquake Engineering Society of Korea. 2018 Apr;22(3):121-128. https://doi.org/10.5000/EESK.2018.22.3.121
  6. Electric Power Research Institute. High Frequency Program, Application Guidance for Functional Confirmation and Fragility Evaluation. EPRI 3002004396. Palo Alto. CA. c2015.
  7. Electric Power Research Institute. Industry Approach to Severe Accident Policy Implementation. NP-7498. Palo Alto. CA. c1991.
  8. Electric Power Research Institute. Program on Technology Innovation: The Effects of HighFrequency Ground Motion on Structures, Components, and Equipment in Nuclear Power Plants. EPRI 1015108. Palo Alto. CA. June Functionality. NP 7148. Palo Alto. CA. c2007.
  9. US Nuclear Regulatory Commission. Regulatory Guide 1.60: Design Response Spectra for Seismic Design of Nuclear Power Plants. US NRC, Washington, D.C., United States. c2014.
  10. Singh MP, Sharma AM. Seismic Floor Spectra by Mode Acceleration Approach. Journal of Engineering Mechanics. 1985;111(11):1402-1419. https://doi.org/10.1061/(ASCE)0733-9399(1985)111:11(1402)
  11. Singh MP. Generation of Seismic Floor Spectra. Journal of Engineering Mechanics. 1975;101(5):593-607.
  12. Reed JW, Kennedy RP. Methodology for Developing Seismic Fragilities EPRI TR-103959. Electric Power Research Institute. Palo Alto. CA. c1994.
  13. Seo JM, Choi IK, Rhee HM, Kim MK. Probabilistic Seismic Hazard Analysis Procedure and Application for Nuclear Power Plant Sites. KAERI/TR-4633. c2012.
  14. Seo JM, Rhee HM, Hahm DG, Kim JH, Choi IK, Kim IK. Development of Ground Motion Response Spectra Considering Site Amplification Effect. KAERI/TR-5373. c2013.
  15. Lee JM. A Study on the Characteristics of Strong Ground Motions in Southern Korea. KINS/HR-422. c2002.
  16. US Nuclear Regulatory Commission. P-CARES: Probabilistic Computer Analysis for Rapid Evaluation. NUREG/CR-6922. c2007. 158p.
  17. Jacekorea. Seismic Fragility and Analysis of Hanul Nuclear Power Plant. Report. Korea. c2015.