Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Improvement of aseismic performance of a PGSFR PHTS pump

  • Lee, Seong Hyeon (Innovative System Technology Development Division, Korea Atomic Energy Research Institute) ;
  • Lee, Jae Han (Innovative System Technology Development Division, Korea Atomic Energy Research Institute) ;
  • Kim, Sung Kyun (Innovative System Technology Development Division, Korea Atomic Energy Research Institute) ;
  • Kim, Jong Bum (Innovative System Technology Development Division, Korea Atomic Energy Research Institute) ;
  • Kim, Tae Wan (Innovative System Technology Development Division, Korea Atomic Energy Research Institute)
  • Received : 2019.09.08
  • Accepted : 2020.01.13
  • Published : 2020.08.25
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Abstract

A design study was performed to improve the limit aseismic performance (LSP) of a primary heat transport system (PHTS) pump. This pump is part of the primary equipment of a prototype generation IV sodium-cooled fast reactor (PGSFR). The LSP is the maximum allowable seismic load that still ensures structural integrity. To calculate the LSP of the PHTS pump, a structural analysis model of the pump was developed and its dynamic characteristics were obtained by modal analysis. The floor response spectrum (FRS) initiated from a safety shutdown earthquake (SSE), 0.3 g, was applied to the support points of the PHTS pump, and then the seismic induced stresses were calculated. The structural integrity was evaluated according to the ASME code, and the LSP of the PHTS pump was calculated from the evaluation results. Based on the results of the modal analysis and LSP of the PHTS pump, design parameters affecting the LSP were selected. Then, ways to improve the LSP were proposed from sensitivity analysis of the selected design variables.

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References

  1. A.P. Villasor JR., Seismic analysis of a reactor coolant pump by the response spectrum method, Nucl. Eng. Des. 38 (1976) 527-542. https://doi.org/10.1016/0029-5493(76)90113-8
  2. K. Fujita, T. Ito, M. Tashimo, A. Sakurai, C. Kurihara, Study on the seismic response of a reactor vessel of a pool type LMFBR including fluid-structure interaction, Nucl. Eng. Des. 113 (1989) 455-462. https://doi.org/10.1016/0029-5493(89)90034-4
  3. Myung J. Jhung, Won G. Hwang, Seismic response of reactor vessel internals for Korean standard nuclear power plant, Nucl. Eng. Des. 165 (1996) 57-66. https://doi.org/10.1016/0029-5493(96)01204-6
  4. J. Buongiorno, B.D. Hawkes, Seismic analysis of heavy-liquid-metal-cooled reactor vessels, Nucl. Eng. Des. 228 (2004) 305-317. https://doi.org/10.1016/j.nucengdes.2003.06.025
  5. P. Chellapandi, S.C. Chetal, Baldev Raj, Effective of nuclear island connected buildings on seismic behavior of reactor internals in a pool type fast breeder reactor, Nucl. Eng. Des. 237 (2007) 2250-2264. https://doi.org/10.1016/j.nucengdes.2007.04.002
  6. R. Lo Frano, G. Pugliese, G. Forasassi, Preliminary seismic analysis of an innovative near term reactor: methodology and application, Nucl. Eng. Des. 240 (2010) 1671-1678. https://doi.org/10.1016/j.nucengdes.2010.02.034
  7. R. Lo Frano, G. Forasassi, Preliminary evaluation of seismic isolation effects in a Generation IV reactor, Energy 36 (2011) 2278-2284. https://doi.org/10.1016/j.energy.2010.04.044
  8. R. Lo Frano, G. Forasassi, Preliminary evaluation of the seismic response of the ELSY LFR, Nucl. Eng. Des. 242 (2012) 361-368. https://doi.org/10.1016/j.nucengdes.2011.10.052
  9. Jigang Meng, Shuhua Yang, Yuefang Wang, Three-Dimensional Seismic Analysis and Safety Evaluation for nuclear pump of nuclear power plant based on the RCC-M Code, Adv.Vib. Eng. 10 (No.4) (2011) 343-352.
  10. ASME Boiler and Pressure Vessel Code, Section III, Division 5, ASME, 2015.
  11. ANSYS Mechanical APDL Manual, Theory Reference (Chapter 15.7 : Spectrum Analysis), Rev. 15.0, ANSYS Inc.
  12. Regulatory Guide 1.92, Combining Modal Responses and Spatial Components in Seismic Response Analysis, Rev. 2, U.S. nuclear regulatory commission, 2006.
  13. ANSYS Mechanical APDL Manual, Rev. 15.0, ANSYS Inc..
  14. S.H. Lee, Structural Analysis of PHTS Pump, KAERI, SFR-230-DM-306-003, 2017 rev01.
  15. G.H. Koo, J.H. Lee, Development of FAMD code to calculate the fluid added mass and damping of arbitrary structures submerged in confined viscous fluid, KSME Int. J. 17 (No.3) (2003) 457-466. https://doi.org/10.1007/BF02984372