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Seismic modeling and analysis for sodium-cooled fast reactor

  • Received : 2010.12.21
  • Accepted : 2012.08.07
  • Published : 2012.08.25

Abstract

In this paper, the seismic analysis modeling technologies for sodium-cooled fast reactor (SFR) are presented with detailed descriptions for each structure, system and component (SSC) model. The complicated reactor system of pool type SFR, which is composed of the reactor vessel, internal structures, intermediate heat exchangers, primary pumps, core assemblies, and core support structures, is mathematically described with simple stick models which can represent fundamental frequencies of SSC. To do this, detailed finite element analyses were carried out to identify fundamental beam frequencies with consideration of fluid added mass effects caused by primary sodium coolant contained in the reactor vessel. The calculation of fluid added masses is performed by detailed finite element analyses using FAMD computer program and the results are discussed in terms of the ways to be considered in a seismic modeling. Based on the results of seismic time history analyses for both seismic isolation and non-isolation design, the functional requirements for relative deflections are discussed, and the design floor response spectra are proposed that can be used for subsystem seismic design.

Keywords

References

  1. ASCE (1986), Seismic Analysis of Safety-Related Nuclear Structures and Commentary on Standard for Seismic Analysis of Safety Related Nuclear Structures, American Society of Civil Engineers.
  2. Chang, Y.I., Finck, P.J., Grandy, C. et al. (2006), Advanced Burner Test Reactor Preconceptual Design Report, ANL-ABR-1, Argonne National laboratory.
  3. Forni, M. and Martelli, A. (1994), Proposal for Design Guidelines for Seismically Isolated Nuclear Plants; Final Report, Contract ETNU-0031-IT (CCSH).
  4. Kim, S.O., Lee, J.H. et al. (2009), Development of Basic Key Technologies for Gen IV SFR, KAERI/RR-3107/ 2009, Korea Atomic Energy Research Institute.
  5. Koo, G.H., Sienicki, J.J., Tzanos, C.P. and Moisseytsev, A. (2009), "Creep-fatigue design evaluations including daily load following operations for the advanced burner test reactor", Nucl. Eng. Des., 239, 1750-1759. https://doi.org/10.1016/j.nucengdes.2009.05.010
  6. Koo, G.H. and Lee, J.H. (2003), "Development of FAMD code to calculate the fluid added mass and damping of arbitrary structures submerged in confined viscous fluid", KSME Int. J., 17(3), 457-466. https://doi.org/10.1007/BF02984372
  7. Lo Frano, R. and Forasassi, G. (2009), "Conceptual evaluation of fluid-structure interaction effect coupled to a seismic event in an innovative liquid metal nuclear reactor", Nucl. Eng. Des., 239, 2333-2342. https://doi.org/10.1016/j.nucengdes.2009.08.008
  8. Lo Frano, R., Pugliese, G. and Forasassi, G. (2010), "Preliminary seismic analysis of an innovative near term reactor: methodology and application", Nucl. Eng. Des., 240, 1671-1678. https://doi.org/10.1016/j.nucengdes.2010.02.034
  9. Micheli, I., Cardini, S., Colaiuda, A. and Turoni, P. (2004), "Investigation upon the dynamic structural response of a nuclear plant on aseismic isolating devices", Nucl. Eng. Des., 228, 319-343. https://doi.org/10.1016/j.nucengdes.2003.06.028
  10. NRC (1973), NRC Reg. Guide1.60, Design Response Spectra for Seismic Design of Nuclear Power Plants, Revision 1, December.
  11. Sigrist, J.F., Broc, D. and Laine, C. (2006), "Dynamic analysis of a nuclear reactor with fluid structure interaction Part I : Seismic loading, fluid added mass and added stiffness effects", Nucl. Eng. Des., 236, 2431- 2443. https://doi.org/10.1016/j.nucengdes.2006.03.001
  12. Su, T.C. (1983), "The effect of viscosity on the forced vibrations of fluid-filled elastic shell", J. Appl. Mech., 50, 517-524. https://doi.org/10.1115/1.3167084
  13. Yang, C.I. and Moran, T.J. (1980), "Calculations of added mass and damping coefficients for hexagonal cylinders in a confined viscous fluid", J. Press. Vessel Technol., 102, 152-157. https://doi.org/10.1115/1.3263314

Cited by

  1. Vertical Seismic Isolation Device for Three-Dimensional Seismic Isolation of Nuclear Power Plant Equipment-Case Study vol.12, pp.1, 2012, https://doi.org/10.3390/app12010320