Seismic Fragility Analysis of PSC Containment Building by Nonlinear Analysis

비선형 지진해석에 의한 PSC 격납건물의 지진취약도 분석

  • Published : 2006.02.28


The seismic fragility analysis method has been used as a quantitative seismic safety evaluation method for the NPP(Nuclear Power Plant) structures and equipments. The seismic fragility analysis gives a realistic seismic capacity excluding the convertism included in the design stage. The conservatism is considered as the probabilistic parameters related to the response and capacity in the seismic fragility analysis. In this study, the displacement based seismic fragility analysis method was proposed based on the nonlinear dynamic analysis results. In this study, the seismic safety of the prestressed concrete containment building of KSNP(Korean Standard Nuclear Power Plant) was evaluated for the scenario earthquakes, neat-fault, far-fault, design earthquake and probability based scenario earthquake, which can be occurred in the NPP sites.


seismic fragility;containment building;nonlinear seismic analysis


  1. US NRC Regulatory Guide 1.60, Design Response Spectra for Seismic Design of Nuclear Power Plants, 1973
  2. Paul Somerville, 'Characterization of Near-Fault Ground Motions,' US-Japan Workshop on the Effects of Near-Field Earthquake Shaking, San Francisco, California, pp.21-29, 2000
  3. Xu, J., Philippacopoulas, A. J., Miller, C. A. and Costantino, C. J., CARES(Computer Analysis for Rapis Evaluation of Structures), NUREC/CR-5588, Vol. 2, 1990
  4. Chopra, A. K., Dynamics of Structures: Theory and Applications to Earthquake Engineering, Prentice- Hall, Inc, 1995
  5. Malhorta, P. K., 'Response of Building to Near-Field Pulse-Like Ground Motions,' Earthquake Engineering and Structural Dynamics, Vol. 28, 1999, pp.1309-1326<1309::AID-EQE868>3.0.CO;2-U
  6. Malhorta, P. K., Effects of Near-Field Pulse-Like Ground Motions on Tall Buildings, 한국지진공학회 추계학술대회 논문집, 1998
  7. Korea Power Engineering Company, Inc. and Sargent & Lundy, 'Design Report : Containment Shell and Dome,' Report No. 9-310-C409-003, Rev. 0, July 16, 1990
  8. ABAQUS, Inc., ABAQUS Version 6.4, 2003
  9. 株式會社 ARK Information System, TDAP III Ver 2.13, 2005
  10. Park, Y. J., Hofmayer, C. H., Technical Guidelines for Aseismic Design of Nuclear Power Plants, Translation of JEAG 4601-1987, NUREG/CR-6241, 1994
  11. Japan Electric Association, Technical Guideliness for a Seismic Design of Nuclear Power Plants, JEAG 4601-1991 Supplement, 1991
  12. Ang ZH-s, Tang, W. H., Probability Concepts in Engineering Planning and Design, Basic Principles, Vol. 1, Wiley, New York, 1975
  13. Read, J. W., Kennedy, R. P., Buttemer, D. R., Idriss, I. M., Moore, D. P., Barr, T., Wooten, K D. and Smith, J. E., A Methodology for Assessment of Nuclear Power Plant Seismic Margin (Revision 1), EPRI NP-6041-SL, 1991
  14. Kennedy, R. P. and Ravindra, M. K., 'Seismic Fragilities for Nuclear Power Plant Risk Studies,' Nuclear Engineering and Design, 79, 1984
  15. Korea Electric Power Company, External Event Analysis for Young-gwang Units 5 & 6 PSA, 2001
  16. Ozaki, M., Okazaki, A., Tomomoto, K., Iba, T., Satoh, R., Nanba, H., Seya, H., Moriyama, K. and Ugata, T. 'Improved Response Factor Methods for Seismic Fragility of Reactor Building,' Nuclear Engineering and Design, 185, 1998
  17. Lee, N.H. and Song, K.B. 'Seismic Capacity Evaluation of the Prestressed/Reinforced Concrete Containment, Young-gwang Nuclear Power Plant Unit 5 & 6,' Nuclear Engineering and Design, 192, 1999, pp.189-203
  18. US NRC Regulatory Guide 1.165, Identification and Characterization of Seismic Sources and Determination of Safe Shutdown Earthquake Ground Motion, 1997