DOI QR코드

DOI QR Code

Round robin analysis to investigate sensitivity of analysis results to finite element elastic-plastic analysis variables for nuclear safety class 1 components under severe seismic load

  • Kim, Jun-Young (Department of Quantum & Nuclear Engineering, Graduate School, Sejong University) ;
  • Lee, Jong Min (Department of Mechanical Engineering, Graduate School, Korea University) ;
  • Park, Jun Geun (Department of Mechanical Engineering, Graduate School, Seoul National University of Science and Technology) ;
  • Kim, Jong-Sung (Department of Quantum & Nuclear Engineering, Sejong University) ;
  • Cho, Min Ki (Doosan Heavy Industries) ;
  • Ahn, Sang Won (SMARTEK E&C) ;
  • Koo, Gyeong-Hoi (Korea Atomic Energy Research Institute) ;
  • Lee, Bong Hee (KEPCO E&C, Inc.) ;
  • Huh, Nam-Su (Department of Mechanical Engineering, Seoul National University of Science and Technology) ;
  • Kim, Yun-Jae (Department of Mechanical Engineering, Korea University) ;
  • Kim, Jong-In (Doosan Heavy Industries) ;
  • Nam, Il-Kwun (KEPCO E&C, Inc.)
  • Received : 2021.04.20
  • Accepted : 2021.07.06
  • Published : 2022.01.25

Abstract

As a part of round robin analysis to develop a finite element elastic-plastic seismic analysis procedure for nuclear safety class 1 components, a series of parametric analyses was carried out on the simulated pressurizer surge line system model to investigate sensitivity of the analysis results to finite element analysis variables. The analysis on the surge line system model considered dynamic effect due to the seismic load corresponding to PGA 0.6 g and elastic-plastic material behavior based on the Chaboche combined hardening model. From the parametric analysis results, it was found that strains such as accumulated equivalent plastic strain and equivalent plastic strain are more sensitive to the analysis variables than von Mises effect stress. The parametric analysis results also identified that finite element density and ovalization option in the elbow elements have more significant effect on the analysis results than the other variables.

Keywords

Acknowledgement

This work was supported by Korea Institute of Energy Technology Evaluation and Planning (KETEP) (No. 20181510102380). "The authors would like to thank Enago (www.enago.co.kr/) for the English language review."

References

  1. ASME Boiler and Pressure Vessels Code Committee, ASME B&PV Code, Section III: Rules for Construction of Nuclear Facility Components, 2019.
  2. G.R. Reddy, Hari Prasad Muruva, Ajit Kumar Verma, Textbook of Seismic Design: Structures, Piping Systems, and Components, Springer, 2019.
  3. US NRC, Recommendations for Enhancing Reactor Safety in the 21st Century: the Near Term Task Force Review of Insights from, Fukushima Dai-Ichi Accident, 2011.
  4. NSC, Regulatory Guide for Reviewing Seismic Design of Nuclear Power Reactor Facilities. NSCRG-1-DS-1.02, 2006.
  5. Izumi Nakamura, Akihito Otani, Masaki Morishita, Seismic qualification of piping systems by detailed inelastic response analysis: part 3 - variation in elastic-plastic analysis results on carbon steel pipes from the benchmark analyses and the parametric analysis, in: Proceedings of ASME PVP 2017. PVP2017-65316, 2017 July 16-20, 2017.
  6. Tomoyoshi Watakabe, Izumi Nakamura, Akihito Otani, Masaki Morishita, Tadahiro Shibutani, Masaki Shiratori, Seismic qualification of piping systems by detailed inelastic response analysis: part 4 - second round benchmark analyses with stainless steel piping component test, in: Proceedings of ASME PVP 2017. PVP2017-65324, 2017 July 16-20, 2017.
  7. JSME, Codes for Nuclear Power Generation Facilities - Rules on Design and Construction for Nuclear Power Plant: Alternative Design for Seismic Design of Seismic S Class Steel Piping Based on Elastic-Plastic Response Analysis. NCCC-008, 2019.
  8. Jong-Sung Kim, Jun-Young Kim, Simplified elastic-plastic analysis procedure for strain-based fatigue assessment of nuclear safety class 1 components under severe seismic loads, Nuclear Engineering and Technology 52 (12) (2020) 2918-2927. https://doi.org/10.1016/j.net.2020.05.008
  9. J.L. Chaboche, Constitutive equations for cyclic plasticity and cyclic viscoplasticity, Int. J. of Plasticity 5 (3) (1989) 247-302. https://doi.org/10.1016/0749-6419(89)90015-6
  10. ASME Boiler and Pressure Vessels Code Committee, ASME B&PV Code, Section II, Part D: Properties Materials, 2019.
  11. G.H. Koo, Inelastic Material Model for Type 316H, ASME BPV III Colorado Springs Meeting Task Group on Inelastic Analysis Methods, 2015. April-26.
  12. https://www.steamtablesonline.com/steam97web.aspx.
  13. APR1400 Design Control Document Tier 2, APR1400-K-X-FS-14002-NP, Revision 0, December 2014.
  14. R.E. Spears, S.R. Jensen, Approach for selection of Rayleigh damping parameters used for time history analysis, J. Pressure Vessel Technol. 134 (2012) 6.
  15. N.R.C. US, Regulatory Guide 1.61, Damping Values for Seismic Design of Nuclear Power Plants, 2007.
  16. Dassault Systems, ABAQUS Version 6.16, User's Manuals, 2016.
  17. ANSYS, Inc., Ansys Academic Research Mechanical, Release 18.1, Help System, Coupled Field Analysis Guide.
  18. https://abaqus-docs.mit.edu/2017/English/SIMACAEEXCRefMap/simaexc-cansysabaproc.htm.
  19. https://en.wikipedia.org/wiki/Timoshenko%E2%80%93Ehrenfest_beam_theory.
  20. https://en.wikipedia.org/wiki/Mindlin%E2%80%93Reissner_plate_theory.