Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
권호 표지
DOI QR코드

DOI QR Code

Seismic fragility evaluation of the base-isolated nuclear power plant piping system using the failure criterion based on stress-strain

  • Kim, Sung-Wan (Seismic Research and Test Center, Pusan National University) ;
  • Jeon, Bub-Gyu (Seismic Research and Test Center, Pusan National University) ;
  • Hahm, Dae-Gi (Integrated Safety Assessment Division, Korea Atomic Energy Research Institute) ;
  • Kim, Min-Kyu (Integrated Safety Assessment Division, Korea Atomic Energy Research Institute)
  • Received : 2018.08.29
  • Accepted : 2018.10.08
  • Published : 2019.04.25
Download PDF
⟨ Previous Next ⟩

Abstract

In the design criterion for the nuclear power plant piping system, the limit state of the piping against an earthquake is assumed to be plastic collapse. The failure of a common piping system, however, means the leakage caused by the cracks. Therefore, for the seismic fragility analysis of a nuclear power plant, a method capable of quantitatively expressing the failure of an actual piping system is required. In this study, it was conducted to propose a quantitative failure criterion for piping system, which is required for the seismic fragility analysis of nuclear power plants against critical accidents. The in-plane cyclic loading test was conducted to propose a quantitative failure criterion for steel pipe elbows in the nuclear power plant piping system. Nonlinear analysis was conducted using a finite element model, and the results were compared with the test results to verify the effectiveness of the finite element model. The collapse load point derived from the experiment and analysis results and the damage index based on the stress-strain relationship were defined as failure criteria, and seismic fragility analysis was conducted for the piping system of the BNL (Brookhaven National Laboratory) - NRC (Nuclear Regulatory Commission) benchmark model.

Keywords

References

  1. A.M. Kammerer, A.S. Whittaker, M.C. Constantinou, Technical Considerations for the Seismic Isolation of Nuclear Facilities," NUREG/CR-xxxx, United States Nuclear Regulatory Commission, Washington, D.C, 2017.
  2. R. Burby, R. Deyle, D. Godschalk, R. Olshansky, Creating Hazard Resilient Communities through land-use Planning, natural Hazards Review, vol. 1, ASCE, 2000, pp. 99-106. https://doi.org/10.1061/(ASCE)1527-6988(2000)1:2(99)
  3. M. Lindell, C. Prater, Assessing Community impacts of natural disasters, Nat. Hazards Rev. 4 (2003) 176-185. https://doi.org/10.1061/(ASCE)1527-6988(2003)4:4(176)
  4. J.Y. Park, K.S. Jan, H.P. Lee, Y.H. Lee, Kim, Experimental study on the temperature dependency of full scale low Hardness lead Rubber bearing, J. Comput. Struct. Eng. Ins. Korea 25 (2012) 533-540. https://doi.org/10.7734/COSEIK.2012.25.6.533
  5. J.M. Kelly, A seismic base isolation: Review and bibliography, Soil Dynam. Earthq. Eng. 5 (1986) 202-216. https://doi.org/10.1016/0267-7261(86)90006-0
  6. N. Kani, Current state of seismic-isolation design, J. Disaster Res. 4 (2008) 175-181. https://doi.org/10.20965/jdr.2009.p0175
  7. M. Forni, A. Poggianti, F. Bianchi, G. Forasassi, R. Lo Frano, G. Pugliese, F. Perotti, L. Corradi dell'Acqua, M. Domaneschi, M.D. Carelli, M.A. Ahmed, A. Maioli, Seismic isolation of the IRIS nuclear plant, in: ASME 2009 Pressure Vessels and Piping Conference, American Society of Mechanical Engineers, Prague, Czech Republic, 2009. PVP2009-78042.
  8. F. Perotti, M. Domaneschi, S.D. Grandis, The numerical computation of seismic fragility of base-isolated nuclear power plants buildings, Nucl. Eng. Des. 262 (2013) 189-200. https://doi.org/10.1016/j.nucengdes.2013.04.029
  9. H.P. Lee, M.S. Cho, A study on the Reduction effect for seismic isolation system of nuclear power plant, in: Proceedings of the 15 World Conference on Earthquake Engineering, Lisbon, Portugal, 2012, p. 30608.
  10. S.H. Eem, H.J. Jung, Seismic fragility assessment of isolated structures by using stochastic response database, Earthquakes and Structures 14 (2018) 389-398. https://doi.org/10.12989/EAS.2018.14.5.389
  11. I. Nakamura, N. Kasahara, Excitation tests on elbow pipe specimens to investigate failure behavior under excessive seismic loads, in: ASME 2015 Pressure Vessels and Piping Conference, Boston, Massachusetts, USA, 2015. PVP2015-45711.
  12. M.K. Kim, O. Yasuki, Y.S. Choun, I.K. Choi, Analysis of seismic fragility improvement effect of an isolated rotational equipment, J. Earthquake Eng. Soc. Korea 11 (2007) 69-78.
  13. ASME Boiler & Pressure Vessel Code, 2007.
  14. N. Kasahara, I. Nakamura, H. Machida, H. Nakamura, Research plan on failure modes by extreme loadings under design extension conditions, in: ASME 2014 Pressure Vessels and Piping Conference, Anaheim, California, USA, 2014. PVP2014-28349.
  15. B.G. Jeon, Seismic Fragility Evaluation of Base Isolated Nuclear Power Plant Piping System (Ph.D. thesis), Pusan National University, 2014.
  16. B.G. Jeon, H.S. Choi, D.G. Hahm, N.S. Kim, Seismic fragility analysis of base isolated NPP piping systems, J. Earthquake Eng. Soc. Korea 19 (2015) 29-36. https://doi.org/10.5000/EESK.2015.19.1.029
  17. B.G. Jeon, S.W. Kim, H.S. Choi, D.U. Park, N.S. Kim, A failure estimation method of steel pipe elbows under in-plane cyclic loading, Nucl. Eng. Technol. 49 (2017) 245-253. https://doi.org/10.1016/j.net.2016.07.006
  18. E.S. Firoozabad, B.G. Jeon, D.G. Hahm, N.S. Kim, Seismic fragility of APR1400 main steam piping system, in: 13th International Conference on Probabilistic Safety Assessment and Management (PSAM 13), Seoul, Korea, 2016. A-576.
  19. E.S. Firoozabad, B.G. Jeon, H.S. Choi, N.S. Kim, Seismic fragility analysis of seismically isolated nuclear power plants piping system, Nucl. Eng. Des. 284 (2015) 264-279. https://doi.org/10.1016/j.nucengdes.2014.12.012
  20. I. Nakamura, A. Otani, M. Shiratori, Comparison of failure modes of piping systems with wall thinning subjected to in-plane, out-of-plane, and mixed mode bending under seismic load: an experimental approach, ASME J. Pressure Vessel Technol. 132 (2010) 031001. https://doi.org/10.1115/1.4001517
  21. G.E. Varelis, S.A. Karamanos, A.M. Gresnigt, Pipe elbows under strong cyclic loading, ASME J. Pressure Vessel Technol. 135 (2013) 011207. https://doi.org/10.1115/1.4007293
  22. K. Yoshino, R. Endou, T. Sakaida, H. Yokota, T. Fujiwaka, Y. Asada, K. Suzuki, Study on seismic design of nuclear power plant piping in Japan-Part 3: component test results, in: ASME 2015 Pressure Vessels and Piping Conference, ASME, 2015, pp. 131-137.
  23. S.W. Kim, B.G. Jeon, H.S. Choi, D.G. Hahm, M.K. Kim, Strain and deformation angle for a steel pipe elbow using image measurement system under in-plane cyclic loading, Nucl. Eng. Technol. 50 (2018) 190-202. https://doi.org/10.1016/j.net.2017.11.001
  24. K. Takahashi, S. Watanabe, K. Ando, A. Hidaka, M. Hisatsune, K. Miyazaki, Low cycle fatigue behaviors of elbow pipe with local wall thinning, Nucl. Eng. Des. 239 (2009) 2719-2727. https://doi.org/10.1016/j.nucengdes.2009.09.011
  25. Y. Urabe, K. Takahashi, K. Sato, K. Ando, Low cycle fatigue behavior and seismic assessment for pipe bend having local wall thinning-influence of internal pressure, J. Pressure Vessel Technol. 135 (2013) 2-6.
  26. H. Banon, H.M. Irvine, J.M. Biggs, Seismic damage in reinforced concrete frames, J. Struct. Div. 107 (1981) 1713-1729. https://doi.org/10.1061/JSDEAG.0005778
  27. J. Gersak, Study of the yield point of the thread, Int. J. Cloth. Sci. Technol. 10 (1989) 244-251. https://doi.org/10.1108/09556229810693654
  28. J.H. Kim, M.K. Kim, I.K. Choi, Response of base isolation system subjected to spectrum matched input ground motions, J. Earthquake Eng. Soc. Korea 17 (2014) 89-95. https://doi.org/10.5000/EESK.2013.17.2.089
  29. ASCE, Seismic Design Criteria for Structures, Systems, and Components in Nuclear Facilities, ASCE 43-05, ASCE, Reston, Virginia, USA, 2005.
  30. ASCE, Seismic Analysis of Safety-related Nuclear Structures and Commentary, ASCE 4-98, ASCE, Reston, Virginia, USA, 2000.
  31. J. Hancock, J. Watson-Lamprey, N.A. Abrahamson, J.J. Bommer, A. Markatis, E. McCoy, R. Mendis, An improved method of matching response spectra of recorded earthquake ground motion using wavelets, J. Earthq. Eng. 10 (2006) 67-89. https://doi.org/10.1080/13632460609350629
  32. B.G. Jeon, H.S. Choi, D.G. Hahm, N.S. Kim, Seismic fragility evaluation of base isolated nuclear power plant piping system, in: Proceedings of the ICTWS 2014 7th International Conference on Thin-walled Structures ICTWS2014, Busan, Korea, 2014. ICTWS2014-0901.
  33. E.S. Firoozabad, B.G. Jeon, H.S. Choi, N.S. Kim, Failure criterion for steel pipe elbows under cyclic loading, Eng. Fail. Anal. 66 (2016) 515-525. https://doi.org/10.1016/j.engfailanal.2016.05.012

Cited by

  1. Evaluation Model of Seismic Response Behavior and Performance of Nuclear Plant Piping Systems vol.11, pp.1, 2019, https://doi.org/10.11004/kosacs.2020.11.1.054
  2. Efficient Seismic Fragility Analysis for Large-Scale Piping System Utilizing Bayesian Approach vol.10, pp.4, 2019, https://doi.org/10.3390/app10041515
  3. 모멘트-변형각의 관계를 이용한 SCH80 3인치 강재배관엘보의 한계상태 평가 vol.24, pp.3, 2020, https://doi.org/10.11112/jksmi.2020.24.3.122
  4. 반복하중 하의 엘보우 변형 및 손상 특성 평가를 위한 모사시험 방법 제안 vol.16, pp.1, 2019, https://doi.org/10.20466/kpvp.2020.16.1.001
  5. Seismic fragility analysis of nuclear power plant structure under far-field ground motions vol.219, 2019, https://doi.org/10.1016/j.engstruct.2020.110890
  6. Quantitative Limit State Assessment of a 3-Inch Carbon Steel Pipe Tee in a Nuclear Power Plant Using a Damage Index vol.13, pp.23, 2019, https://doi.org/10.3390/en13236395
  7. 주기적 하중을 받는 SCH 40 3-Inch 탄소강관엘보의 소산에너지 기반의 손상지수 평가 vol.25, pp.1, 2021, https://doi.org/10.11112/jksmi.2021.25.1.112
  8. A hybrid seismic isolation system toward more resilient structures: Shaking table experiment and fragility analysis vol.38, 2019, https://doi.org/10.1016/j.jobe.2021.102194
  9. Study on Inelastic Strain-Based Seismic Fragility Analysis for Nuclear Metal Components vol.14, pp.11, 2021, https://doi.org/10.3390/en14113269
  10. Seismic Performance of Piping Systems of Isolated Nuclear Power Plants Determined by Numerical Considerations vol.14, pp.13, 2019, https://doi.org/10.3390/en14134028
  11. Optimal Earthquake Intensity Measures for Probabilistic Seismic Demand Models of Base-Isolated Nuclear Power Plant Structures vol.14, pp.16, 2019, https://doi.org/10.3390/en14165163
  12. Mitigation of seismic responses of actual nuclear piping by a newly developed tuned mass damper device vol.53, pp.8, 2019, https://doi.org/10.1016/j.net.2021.02.009
  13. Probabilistic seismic fragility assessment of isolated nuclear power plant structure using IDA and MSA methods vol.34, 2019, https://doi.org/10.1016/j.istruc.2021.08.034
  14. Evaluation of the Limit State of a Six-Inch Carbon Steel Pipe Elbow in Base-Isolated Nuclear Power Plants vol.14, pp.24, 2019, https://doi.org/10.3390/en14248400
  15. Experimental study on the floor responses of a base-isolated frame structure via shaking table tests vol.253, 2019, https://doi.org/10.1016/j.engstruct.2021.113763