AN ANALYSIS OF DISCRETIZATION EFFECT OF MOMENTUM CONVECTION TERM FOR MULTI-DIMENSIONAL TWO-PHASE FLOWS

운동량 방정식의 대류항 이산화 방법이 다차원 2상 유동 해석에 미치는 영향 분석

  • Published : 2009.09.30

Abstract

The non-conservative form of momentum equations is often used for some two-phase flow codes instead of a conservative form because of numerical convenience. Another non-conservative form, so called, a semi-conservative form can improve the numerical solution of these codes maintaining the numerical convenience. It is close to the conservative form but still maintains the feature of the non-conservative form. A semi-conservative form of the momentum equations and a non-conservative form of the momentum equations are implemented in CUPID[1] code. The numerical results of the semi-conservative and the non-conservative forms are compared against analytical solutions and the solutions of the FLUENT code that uses the conservative form. The results clearly showed that the semi-conservative form of the momentum equations provides better solutions than the non-conservative form, especially for heterogeneous two-phase flows.

Keywords

References

  1. 2007, Jeong, J.J., Yoon, H.Y., Cho, H.K., Kim, J. and Park, I.K., "Hydrodynamic Solver for a Transient Two-Fluid Three-Field Model on Unstructured Grids," J. Korean Society of Computational Fluids Engineering, Vol.12, No.4,pp.44-53
  2. 1978, Liles, D.R. and Reed, W.H., "A semi-implicit method for two-phasefluid dynamics," Journal of ComputationalPhysics, Vol.26, pp.390-407 https://doi.org/10.1016/0021-9991(78)90077-3
  3. 2001, The RELAP5-3D code development team, RELAP5-3D code manual volume I: Code structure, system models and solution methods, Idaho National Engineering and Environmental Laboratory
  4. 1997, Jeong, J.J., Dor, I. and Bestion, D., "Improvement and assessment of the CATHARE2 three-dimensional module compared with the uptf downcomer test 7," NuclearTechnology, Vol.117, pp.267-280
  5. 1999, Jeong, J.J., Ha, K.S., Chung, B.D. and Lee, W.J., "Development of a multi-dimensional thermal-hydraulic system code: MARS 1.3.1," Annals of Nuclear Energy,Vol.26, No.18, pp.1611-1642 https://doi.org/10.1016/S0306-4549(99)00039-0
  6. 1993, Spore, J.W. et al., TRAC-PF1/MOD2 Volume I. Theory manual, NUREG/CR-5673, Los Alamos National Laboratory
  7. 2000, TRACE V5.0, Theory manual, U.S. Nuclear Regulatory Commission
  8. 2007, Guelfi, A. et al., "NEPTUNE: A new software platform for advanced nuclear thermal hydraulics," NuclearScience and Engineering, Vol.156, No.3, pp.281-324
  9. 2008, Yoshida, H., Ohnuki, A., Misawa, Takase, T. and Akimoto, K., "Development of analytical procedures of two-phase flow in tight-lattice fuel bundles for innovative water reactor for flexible fuel cycle," Nuclear Technology, Vol.164, pp.45-54 https://doi.org/10.13182/NT08-A4007
  10. 2006, FLUENT 6.3, User's guide, FLUENT Inc
  11. 2005, ANSYS CFX-Solver, Release 10.0: Theory, ANSYS Inc
  12. 2006, STAR-CD version 4.0, STAR-CD Methodology,CD-adapco
  13. 2000, Spore, J.W. et al., TRAC-M/Fortran 90 (Version 3.0),Theory Manual, Los Alamos National Laboratory
  14. 1983, Rhie, C.M. and Chow, W.L., "Numerical study of the turbulent flow past an airfoil with trailing edge separation,"AIAA Journal, Vol.21, No.11, pp.1525-1532 https://doi.org/10.2514/3.8284
  15. 2006, Staedtke, H., Gas dynamic aspects of two-phase flow, Wliey-VCH Verlag GmbH & Co, KGaAWeinheim,pp.143-147