Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
권호 표지
DOI QR코드

DOI QR Code

Effect of slab stiffness on floor response spectrum and fragility of equipment in nuclear power plant building

  • Yousang Lee (Department of Architecture and Architectural Engineering, Seoul National University) ;
  • Ju-Hyung Kim (Department of Civil Engineering, University of Colorado Denver) ;
  • Hong-Gun Park (Department of Architecture and Architectural Engineering, Seoul National University)
  • Received : 2023.02.23
  • Accepted : 2023.07.07
  • Published : 2023.11.25
Download PDF
⟨ Previous Next ⟩

Abstract

The floor response spectrum (FRS) is used to evaluate the seismic demand of equipment installed in nuclear power plants. In the conventional design practice of NPP structure, the FRS is simplified using the lumped-mass stick model (LMSM), assuming the floor slab as a rigid diaphragm. In the present study, to study the variation of seismic response in a floor, the FRSs at different locations were generated by 3-D finite element model, and the response was compared to that of the rigid diaphragm model. The result showed that the FRS significantly varied due to the large opening in a floor, which was not captured by the rigid diaphragm model. Based on the result, seismic fragility analysis was performed for the anchorage of a heat exchanger, to investigate the effect of location-dependent FRS disparity on the high confidence low probability of failure (HCLPF).

Keywords

Acknowledgement

This work was supported by the National Research Foundation of Korea(NRF) grant funded by the Korea Government(MSIT) (No. RS2022-00144409).

References

  1. E.H. Lee, J.M. Kim, K.H. Joo, H. Kim, Evaluation of the soil-structure interaction effect on seismically isolated nuclear power plant structures, J. Earthq. Eng. Soc. Korea 20 (2016) 379-389. 
  2. V. Varma, G.R. Reddy, K.K. Vaze, H.S. Kushwaha, Simplified approach for seismic analysis of structures, Int. J. Struct. Stabil. Dynam. 2 (2) (2002) 207-225. 
  3. Y.-N. Huang, A.S. Whittaker, N. Luco, Seismic performance assessment of base-isolated safety-related nuclear strucures, Earthq. Eng. Struct. Dynam. 39 (13) (2010) 1421-1442. 
  4. D.D. Nguyen, B. Thusa, T.S. Han, T.H. Lee, Identifying significant earthquake intensity measures for evaluation seismic damage and fragility of nuclear power plant structures, Nucl. Eng. Technol. 50 (1) (2020) 192-205. 
  5. J.R. Nie, C.H. Hofmayer, J.I. Braverman, S.P. Stovall, A study of the effect of floor flexibility on building response using the KK NPP experience, in: Transactions of the 22nd International Conference on the Structural Mechanics in Reactor Technology, 2013. San Francisco, California, USA, August 18-23. 
  6. B.B. Torkian, P. Chandran, B.J. Ratnagaran, R. Miller, S. Lu, Validation of lumped mass stick models for surface founded structures, in: Transactions of the 22nd International Conference on the Structural Mechanics in Reactor Technology, 2013. San Francisco, California, USA, August 18-23. 
  7. G. Hardy, R. Soto, S. Short, R. Kassawara, Finite element and lumped mass structure modelling for SPRAs, in: Transactions of the 23rd International Conference on the Structural Mechanics in Reactor Technology, 2015. Manchester, United Kingdom, August 10-14. 
  8. T. Radford, S. Damolini, J. O'Sullivan, A case study on the effect of detailed 3D finite element modelling on nuclear power plant building response, in: Transactions of the 23rd International Conference on the Structural Mechanics in Reactor Technology, 2015. Manchester, United Kingdom, August 10-14. 
  9. S. El-Bahey, S. Damolini, T. Radford, C. Figliolini, Seismic SSI analysis comparison between detailed and discretized modeling of an auxiliary control building, in: Transactions of the 24th International Conference on the Structural Mechanics in Reactor Technology, 2017. Busan, Korea, August 20-25. 
  10. S. Damolini, S. El-Bahey, K. Oikonomou, Seismic SSI analysis comparison between detailed and discretized modeling of an auxiliary/control building, in: Transactions of the 25th International Conference on the Structural Mechanics in Reactor Technology, August 2019. Charlotte NC, USA. 
  11. I.-K. Choi, Review and proposal for seismic safety assessment of nuclear power plants against beyond design basis earthquake, Transaction of the KPVP 13 (1) (2017) 1-15 (in Korean). 
  12. U.S. NRC, Development of Criteria for Seismic Review of Selected Nuclear Power Plants, U.S. Nuclear Regulatory Commission, Washington, 1978. DC NUREG/CR-0098. 
  13. ASCE, Seismic Analysis of Safety-Related Nuclear Structures, American Society of Civil Engineers, Reston, VA, 2017. ASCE/SEI 4-16. 
  14. U.S. NRC, Technical Basis for Revision of Regulatory Guidance on Design Grond Motions: Hazard-and Risk-Consistent Ground Motion Spectra Guidelines, U.S. Nuclear Regulatory Commission, Washington DC, 2001. NUREG/CR-6728. 
  15. NIST, Selecting and Scaling Earthquake Ground Motions for Performing Response-History Analyses, National Institute of Standards and Technology, Gaithersburg, ML, 2011. NIST GCR 11-917-15. 
  16. U.S. NRC, Standard Review Plan, Revision 4, U.S. Nuclear Regulatory Commission, Washington, DC, 2014. NUREG-0800. 
  17. A.R. Kottke, E.M. Rathje, Technical Manual for Strata. Pacific Earthquake Engineering Research Center, University of California, Berkeley, 2008. Report No.2008/10. 
  18. G.R. Toro, Probabilistic Models of Site Velocity Profiles for Generic and Site-specific Ground-Motion Amplification Studies, Brookhaven National Laboratory, 1995. 
  19. M.B. Darendeli, Development of a New Family of Normalized Modulus Reduction and Material Damping Curves, The University of Texas, Austin, TX, 2001. 
  20. ANSYS, Inc., Ansys® Mechanical, Release 20.2, 2020. Canonsburg, PA. 
  21. ACI Committee 318, Building Code Requirements for Structural Concrete, American Concrete Institute, Farmington Hills, MI, 2019, pp. 318-319. 
  22. U.S. NRC, Damping Values for Seismic Design of Nuclear Power Plants, Revision 1, U.S. Nuclear Regulatory Commission, Washinton DC, 2007. RG 1.61. 
  23. KEPCO & KHNP, Finite Element Seismic Models for SSI Analyses of the NI Buildings of the APR1400 Standard Plant, Korea Electric Power Corporation & Korea Hydro & Nuclear Power Co., Ltd, 2013, ML13304A931. 
  24. EPRI, Seismic Fragility and Seismic Margin Guidance for Seismic Probabilistic Risk Assessments, Electric Power Research Institute, Palo Alto, CA, 2018. EPRI-3002012994. 
  25. R.P. Kennedy, C.A. Cornell, R.D. Campbell, S. Kaplan, H.F. Perla, Probabilistic seismic safety study of an existing nuclear power plant, Nucl. Eng. Des. 59 (2) (1980) 315-338. 
  26. MATLAB, 9.11.0.1809720 (R2021b), The MathW orks Inc., Natick, Massachusetts, 2018. 
  27. KEPCO & KHNP, Seismic Design Bases for the APR1400 Standard Plant Design, Korea Electric Power Corporation & Korea Hydro & Nuclear Power Co., Ltd., 2013. APR1400-E-S-NR-13001-NP. 
  28. KEPCO & KHNP, Status Report - APR1400 (KEPCO E&C/KHNP), Korea Electric Power Corporation & Korea Hydro & Nuclear Power Co., Ltd., 2020. 
  29. M.K. Kim, I.-K. Choi, A shaking table test for an Re-evaluation of seismic fragility of electrical cabinet in NPP, J. Comput. Struct. Eng. Inst. Korea 24 (3) (2011) 295-305. 
  30. G.K. Kulak, J.W. Fisher, J.H.A. Struik, Guide to Design Criteria for Bolted and Riveted Joints, Wiley & Son, New York, 1987. 
  31. ACI Committee 349, Code Requirements for Nuclear Safety-Related Concrete Structures and Commentary, American Concrete Institute, Farmington Hills, MI, 2013. ACI 349-13. 
  32. R. Eligehausen, T. Balogh, Behavior of fasteners loaded in tension in cracked reinforced concrete, Structural Journal 92 (3) (1995) 365-379. 
  33. R. Eligehausen, R. Mallee, J.F. Silve, Anchorage in Concrete Construction, Ernst & Sohn, Berlin, Germany, 2006. 
  34. H.H.M. Hwang, Determination of HCLPF value for seismic margins study, in: Transactions of the 10th SMiRT, 1989. Anaheim, CA, USA, August 22-27.