Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Application of Hyperbolic Two-fluids Equations to Reactor Safety Code

  • Published : 2003.02.01
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Abstract

A hyperbolic two-phase, two-fluid equation system developed in the previous work has been implemented in an existing nuclear safety analysis code, MARS. Although the implicit treatment of interfacial pressure force term introduced in momentum equation of the hyperbolic equation system is required to enhance the numerical stability, it is very difficult to implement in the code because it is not possible to maintain the existing numerical solution structure. As an alternative, two-step approach with stabilizer momentum equations has been selected. The results of a linear stability analysis by Von-Neumann method show the equivalent stability improvement with fully-implicit solution method. To illustrate the applicability, the new solution scheme has been implemented into the best-estimate thermal-hydraulic analysis code, MARS. This paper also includes the comparisons of the simulation results for the perturbation propagation and water faucet problems using both two-step method and the original solution scheme.

Keywords

References

  1. Lyczkowski, R.W., Gidaspow, D., Solbrig, C.W., and Hughes, E. D., 1978, Characteristics and stability analysis of transient one-dimensional two-phase flow equations and their finite difference approximations, Nucl. Sci. Eng., 66, 378 https://doi.org/10.13182/NSE78-4
  2. Lim. H.G. et al, 2001, 'Application of Stability Enhancing Minmum Interfacial Pressure Force Model for MARS,' KAERI/TR-1784/2001
  3. Stuhmiller, J.H., 1977, 'The influence of Interfacial Pressure Forces on the Character of the Two-phase Flow model Equations,' Int. J. Multiphase Flow 3, 551-560 https://doi.org/10.1016/0301-9322(77)90029-5
  4. Strikwerda, J.A., 1989, Finite Difference Schemes and Partial Differential Equations, Wadsworth & Brooks/Cole Advanced Books & Software Pacific Grove, California
  5. Jeong, J.J., Ha, K.S., Chung, B.D., Lee, W.J., 'Development of A Multi-dimensional Thermal-Hydraulic System Code, MARS1.3.1,' Annals of Nuclear Energy 26(18), 1161-1642(1999) https://doi.org/10.1016/S0306-4549(99)00039-0
  6. Holmes, M.A., 1995, Stability of Finite Difference Approximations of Two Fluid, Two Phase Flow Equations, Ph.D. Thesis, NCSU, Raleigh
  7. Ransom, V.H., 1979, 'Faucet Flow, Oscilating Manometer, and Expulsion of Steam by Subcooled Water,' Part 3, Numerical Benchmark Tests, Multiphase Science and Technology, Volume 3
  8. Carlson, K.E., Riemke, R.A., Rouhani, S.Z., Shumway, R.W., Weaver, W. L., RELAP5/MOD3 code manual volume 1: code structure, system models, and solution methods(draft), NUREG/CR-5535, EGG-2596, EG&G Idaho, Inc., June(1990)
  9. Kim, K.D., Lee, S.J., Chang, W.P., ;Ha, E.J., Jeun, G. D., 1998, Numerical Stability Analysis of New Hyperbolic Equations for Two-Phase Flow, Proc. 6th International Conference on Nuclear Engineering, San Diego
  10. TRAC-PF1/MOD1: An advenced best-estimate computer program for pressurized water reactor thermal-hydraulic analysis, NUREC/CR-3858, LA-10157-MS, Los Alamos National Laboratory, (1986)