Journal of the Earthquake Engineering Society of Korea (한국지진공학회논문집)

Earthquake Engineering Society of Korea (한국지진공학회)
권호 표지
DOI QR코드

DOI QR Code

Seismic Fragility Analysis of Base Isolated NPP Piping Systems

지진격리된 원전배관의 지진취약도 분석

  • Received : 2014.05.29
  • Accepted : 2014.11.17
  • Published : 2015.01.01
Download PDF
⟨ Previous Next ⟩

Abstract

Base isolation is considered as a seismic protective system in the design of next generation Nuclear Power Plants (NPPs). If seismic isolation devices are installed in nuclear power plants then the safety under a seismic load of the power plant may be improved. However, with respect to some equipment, seismic risk may increase because displacement may become greater than before the installation of a seismic isolation device. Therefore, it is estimated to be necessary to select equipment in which the seismic risk increases due to an increase in the displacement by the installation of a seismic isolation device, and to perform research on the seismic performance of each piece of equipment. In this study, modified NRC-BNL benchmark models were used for seismic analysis. The numerical models include representations of isolation devices. In order to validate the numerical piping system model and to define the failure mode, a quasi-static loading test was conducted on the piping components before the analysis procedures. The fragility analysis was performed by using the results of the inelastic seismic response analysis. Inelastic seismic response analysis was carried out by using the shell finite element model of a piping system considering internal pressure. The implicit method was used for the direct integration time history analysis. In addition, the collapse load point was used for the failure mode for the fragility analysis.

Keywords

References

  1. U.S Nuclear Regulatory Commission. Technical Considerations for Seismic Isolation of Nuclear Facilities(Draft);c2012.
  2. Choi IK, Seo JM. Inelastic Energy Absorption Factor for the Seismic Probabilistic Risk Assessment of NPP Containment Structure. Journal of the Earthquake Engineering Society of Korea. 2001;5(5): 47-56.
  3. Choi IK, Seo JM, Chun, YS, Lee, JR. Evaluation of Response Spectrum Shape Effect on Seismic Fragility of NPP Component. Journal of the Earthquake Engineering Society of Korea. 2003;7(4): 23-30. https://doi.org/10.5000/EESK.2003.7.4.023
  4. Kim MK, Yasuki O, Chun YS, Choi IK. Analysis of Seismic Fragility Improvement Effect of an Isolated Rotational Equipment. Journal of the Earthquake Engineering Society of Korea. 2007;11(6):69-78. https://doi.org/10.5000/EESK.2007.11.6.069
  5. KHNP. Probabilistic Safety Assessment of Uljin No. 5 and No. 6;2002.
  6. Xu, J, DeGrassi, G, Chokshi, N. A NRC-BNL benchmark evaluation of seismic analysis methods for non-classically damped coupled systems. Nuclear Engineering and Design. 2004;228:345-366. https://doi.org/10.1016/j.nucengdes.2003.06.019
  7. Huang YN, Andrew S, Whittaker A, Nicolas L. Seismic Performance Assessment of Base-isolated Safety-related Nuclear Structures, Earthquake Engineering and Structural Dynamics. 2010;39:1421-1442. https://doi.org/10.1002/eqe.1038
  8. Touboul F, Sollogoub P, Blay N. Seismic behaviour of piping systems with and without detect : experimental and numerical evaluations. Nuclear Engineering and Design. 1999;192:243-260. https://doi.org/10.1016/S0029-5493(99)00111-9
  9. Zhang T, Brust FW, Shim DJ, Wikowski G, Nie J, Hofmayer C. Analysis of JNES Seismic Tests on Degraded Piping. NUREG/CR-7015; c2010.
  10. American Society of Mechanical Engineers. Welded and Seamless Wrought Steel Pipe, ASME B36.10M-2004;c2004.
  11. Gye MS. A Research of Elbow Wall Thickness Effect in Nuclear Power Plant Piping System. Ph.d thesis. Pusan National University;c2013.
  12. KEPCO Engineering & Construction Company, Inc. SKN 3 & 4 Safety Related-Plant Manual-Main Stem System (MS), 9-521-M442-001; c2011.
  13. American Society of Mechanical Engineers. ASME Boiler & Pressure Vessel Code;c2007.
  14. Electric Power Research Institute, Piping and Fitting Dynamic Reliability Program. EPRI TR-102792-V1 through V5;c1994.
  15. Ju BS, Jung WY. Framework for Fragility Evaluation of Piping System. The 22nd International Conference on Structural Mechanics in Reactor Technology (SMiRT-22);c2013.
  16. American Society of Civil Engineers. Seismic Design Criteria for Structures, Systems, and Components in Nuclear Facilities. ASCE 43-05;c2005.
  17. American Society of Civil Engineers. Seismic Analysis of Safety-Related Nuclear Structures and Commentry. ASCE 4-98;c2000.
  18. Kim JH, Kim MK, Choi IK. Response of Base Isolation System Subjected to Spectrum Matched Input Ground Motions. Journal of the Earthquake Engineering Society of Korea. 2013;17(2):89-95. https://doi.org/10.5000/EESK.2013.17.2.089
  19. U.S Nuclear Regulatory Commission. Regulatory Guide. 1.60, Design Response Spectra for Seismic Design of Nuclear Power Plants;c1973.
  20. Hancock J, Watson-Lamprey J, Abrahamson NA, Bommer JJ, Markatis A, McCoy E, Mendis R. An improved method of matching response spectra of recorded earthquake ground motion using wavelets. Journal of Earthquake Engineering. 2006;10(S1): 67-89.

Cited by

  1. Seismic Surface Wave Cloaking by Acoustic Wave Refraction vol.19, pp.6, 2015, https://doi.org/10.5000/EESK.2015.19.6.257