DOI QR코드

DOI QR Code

Seismic Performance Evaluation of Piping System Crossing the Isolation Interface in Seismically Isolated NPP

면진 원전 면진-비면진구간 연결 배관의 내진성능 평가

  • Received : 2014.02.20
  • Accepted : 2014.04.15
  • Published : 2014.05.01

Abstract

A methodology to evaluate the seismic performance of interface piping systems that cross the isolation interface in the seismically isolated nuclear power plant (NPP) was developed. The developed methodology was applied to the safety-related interface piping system to demonstrate the seismic performance of the target piping system. Not only the seismic performance for the design level earthquakes but also the performance for the beyond design level earthquakes were evaluated. Two artificial seismic ground input motions which were matched to the design response spectra and two historical earthquake ground motions were used for the seismic analysis of piping system. The preliminary performance evaluation results show that the excessive relative displacements can occur in the seismically isolated piping system. If the input ground motion contained relatively high energy in the low frequency region, we could find that the stress response of the piping system exceed the allowable stress level even though the intensity of the input ground motion is equal to the design level earthquake. The structural responses and seismic performances of piping system were varied sensitively with respect to the intensities and frequency contents of input ground motions. Therefore, for the application of isolation system to NPPs and the verification of the safety of piping system, the seismic performance of the piping system subjected to the earthquake at the target NPP site should be evaluated firstly.

Keywords

References

  1. Kim HU. Evaluation of the Applicability of Existing Design Formula for Seismic Isolation to Nuclear Power Plants. Journal of the Earthquake Engineering Society of Korea. 2012;16(6):29-36. https://doi.org/10.5000/EESK.2012.16.6.029
  2. Jung HJ, Eem SH, Kim MK, Choi IK. Seismic Fragility Evaluation of Isolated NPP Containment Structure Considering Soil-Structure Interaction Effect. Journal of the Earthquake Engineering Society of Korea. 2013;17(2):53-59. https://doi.org/10.5000/EESK.2013.17.2.053
  3. 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
  4. Kim HU, Joo KH, Noh SH, Jung CG. Behavior Analysis of a Seismically Isolated NPP Structure by Varying Seismic Input Generation Method and Strong Ground Motion Duration. Journal of the Earthquake Engineering Society of Korea. 2013;17(4):187-195. https://doi.org/10.5000/EESK.2013.17.4.187
  5. Hong KJ, Lee JH, Kim JK. Characteristics of Earthquake Responses of an Isolated containment Building in Nuclear Power Plants According to Natural Frequency of Soil. Journal of the Earthquake Engineering Society of Korea. 2013;17(6):245-255. https://doi.org/10.5000/EESK.2013.17.6.245
  6. Zhang T, Brust FW, Shim DJ, Wikowski G, Nie J, Hofmayer C. Analysis of JNES Seismic Tests on Degraded Piping. NUREG/CR-7015; BNL-NUREG-91346-2010; Brookhaven National Laboratory; c2010.
  7. DeGrassi G, Nie J, Hofmayer C. Seismic Analysis of Large-Scale Piping Systems for the JNES-NUPEC Ultimate Strength Piping Test Program. NUREG/CR-6983, BNL-NUREG-81548-2008; Brookhaven National Laboratory; c2010.
  8. Cheung JH, Gae MS, Seo YD, Choi HS, Kim MK. Seismic Capacity Test of Nuclear Piping System using Multi-platform Shake Table. Journal of the Earthquake Engineering Society of Korea. 2013;17(1): 21-31. https://doi.org/10.5000/EESK.2013.17.1.021
  9. ASME. ASME CODE Section III, Division I, Subsection NB. ASME standard; c2007.
  10. Kim IT, Kim KJ, Seo YD, Choi SJ, Kim MH, Choi HS, Moon SJ. Ultimate-level Seismic Performance Evaluation of a Piping System. KAERI/CM-1402/2010; Korea Atomic Energy Research Institute; c2010.
  11. Lemaitre J, Chaboche JL, Shribastava B. Mechanics of Solid Materials. Cambridge University Press; c2002.
  12. Computer and structures Inc. SAP2000: Analysis Reference; Berkeley; 1995.
  13. U.S. NRC. Design Response Spectra for Sesimc Design of Nuclear Power Plants. U.S. NRC Regulatory Guide 1.60; c1973.