Transactions of the Korean Society of Pressure Vessels and Piping (한국압력기기공학회 논문집)

Korean Society of Pressure Vessels and Piping (한국압력기기공학회)
권호 표지
DOI QR코드

DOI QR Code

A Plan to Develop Seismic Capacity Verification Procedures Based on the Elastic-Plastic Strain Features

탄소성 변형률 기반 내진성능 평가 절차서 개발 방안

  • Received : 2018.09.27
  • Accepted : 2018.11.07
  • Published : 2018.12.30
Download PDF
⟨ Previous Next ⟩

Abstract

A development plan for seismic capacity verification procedures of nuclear components based on the elastic-plastic strain (EPS) features is explained in this paper. The EPS methodology is more realistic to assess seismic responses of components to extreme seismic events beyond the safe shutdown earthquake (SSE) than current practices with the criteria of stress limits. The EPS based approach to analyze the seismic capacity of components can reduce over-conservatism in the current stress-based criteria and can incorporate the seismic responses of components deformed in plastic behavior by the motion of extreme earthquake.

Keywords

References

  1. NSSC No. 17, 2016, "Regulations on Technical Standards for Nuclear Reactor Facilities," Nuclear Safety and Security Commission, Seoul.
  2. Hwang, J. K., Jeong, I. S., Kim, B. S. and So, J. Y., 2018, "Lessons Learned from Seismic Fragility Tests of Nuclear Piping Systems," Trans. of KSME Chungcheong Branch Spring Conference, Daejeon, pp. 69-72.
  3. MOTIE, 2014, The Second Plan for National Energy Supply.
  4. KEPIC END 2000, 2015, "Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations," Korea Electric Association, Seoul.
  5. KEPIC END 1100, 2015, "Qualifying Class 1E Equipment for Nuclear Power Generating Stations," Korea Electric Association, Seoul.
  6. KEPIC MNB, 2015, "Nuclear Mechanical, Class 1 Components," Korea Electric Association, Seoul.
  7. Yang, H., Sinha, S. K., Feng, Y., Mc-Callen, D. B. and Jeremic, B., 2017, "Energy Dissipation Analysis of Elastic-Plastic Materials," Comput. Method Appl. M, Vol. 331, pp. 309-326.
  8. An Utility, 2017, Development of Technology for Structural Integrity Evaluation of Major Components, A Private propriety.
  9. EPZ, 2011, "Complementary Safety Margin Assessment, Final Report," pp.2.26-2.30
  10. Lee, D. Y., Park, H. B., Kim, J. W. and Kim, Y. J., 2016, "Strain-Based Structural Integrity Evaluation Methods for Nuclear Power Plant Piping under Beyond Design Basis Earthquake," Trans. of the KPVP, Vol. 12, No. 2, pp. 56-61.
  11. Kim, J. S., Kim, J. W., Kim Y. J. and Kwon, H. D., 2017, "Development of Effective Elastic-Plastic Dynamic Analysis and Strain Based Assessment for Time History Seismic Analysis of Major Components of Nuclear Power Plants," The 33th MAGIC CoP Meeting, Presentation Material, KINS, Daejeon.
  12. ASME BPVC Sec. III Div.1 Sub. NB, 2017, "Rules for Construction of Nuclear Facility Components," America Society of Mechanical Engineers, NY.
  13. ASME BPVC Sec. III App.FF, 2017, "Strain-Based Acceptance Criteria for Energy-Limited Events," America Society of Mechanical Engineers, NY.
  14. ASME BPVC Sec. VIII Part 5, 2015, "Design by Analysis Requirements," America Society of Mechanical Engineers, NY.
  15. Morishita, M., Akihito O., Tomoyoshi W., Izumi N., Tadahiro S. and Masaki S., 2017, "Seismic Qualification of Piping Systems by Detailed Inelastic Response Analysis, Part 1- A Code Case for Piping Seismic Evaluation Based on Detailed Inelastic Response Analysis," Proc. of ASME 2017 PVP Conference, Waikoloa, HW, July 16-20, PVP2017-65166.
  16. Adams, T. M., 2015, "Basis of the Upcoming Changes to Piping Seismic Design Rules in the ASME BPVC Section III, Division 1, Article NB-3200," Proc. of ASME 2017 PVP Conference, Boston, MA, July 19-23, PVP2015-45697.
  17. EPRI, 1990, "Guidelines for development of in-cabinet amplified response spectra for electrical benchboards and panels," Electric Power Research Institute, Palo Alto, CA, EPRI-NP-7146-M.
  18. EPRI, 1995, "Guidelines for Development of In-Cabinet Seismic Demand for Devices Mounted in Electrical Cabinets," Electric Power Research Institute, Palo Alto, CA, NP-7146-SL R1.
  19. USNRC, 2011, "Evaluation of JNES Equipment Fragility Tests for Use in SPRA for US NPPs," U.S. Nuclear Regulatory Commission, Washington, D.C., NUREC/CR-7040.