Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Flow Analysis for Optimum Design of Mixing Vane in a PWR Fuel Assembly

  • Published : 2001.06.01
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Abstract

A computational fluid dynamics (CFD) analysis was performed to propose the optimum design of flow mixing vane on the space grid in a PWR fuel assembly. The flow mixing vanes considered in this study for optimum design are swirl-vane and twisted-vane. A single subchannel of one grid span was modeled using flow symmetry to minimize the computational effort. The CFD predictions are in good agreement with the experimental results for the split- vane, which shows the applicability of the CFD method. The mixing effect by swirling flow and crossflow, and the pressure drop were estimated and compared for the various vane angles. The optimum vane angle is proposed to be 40。 and 35。 from the direction of axial flow for the swirl-vane and the twisted-vane, respectively.

Keywords

References

  1. D. S. Rowe, B. M. Johnson and J. G. Knudsen, 'Implications Concerning Rod Bundle Crossflow Mixing Based on Measurements of Turbulent Flow Structure,' International Journal Heat Mass Transfer, 17, 407 (1974)
  2. S. V. Moller, 'On Phenomena of Turbulent Flow through Rod Bundles,' Experiments in Thermal and Fluid Science, 4, 25 (1991) https://doi.org/10.1016/0894-1777(91)90018-M
  3. K. Rehme, 'The Structure of Turbulence in Rod Bundles and the Implications on Natural Mixing Between the Subchannels,' International Journal of Heat and Mass Transfer, 35, 567 (1992) https://doi.org/10.1016/0017-9310(92)90291-Y
  4. Y. F. Shen, Z. D. Cao and Q. G. Lu, 'An Investigation of Crossflow Mixing Effect Caused by Grid Spacer with Mixing Blades in a Rod Bundle,' Nuclear Engineering and Design, 125, 111 (1991)
  5. Z. Karoutas, C. Y. Gu and B. Scholin, '3-D Flow Analyses for Dsign of Nuclear Fuel Spacer,' Proc. of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics, New-York, United Sates, September, (1995)
  6. S. K. Yang and M. K. Chung, 'Spacer Grid Effects on Turbulent Flow in Rod Bundles,' Journal of the Korean Nuclear Science, 28, 56 (1996)
  7. M. Imaizumi, T. Ichioka, M. Hoshi, H. Teshima, H. Kobayashi and T. Yokoyama, 'Development of CFD Method to Evaluate 3-D Fow Characteristics for PWR Fuel Assembly,' Trans. of the 13th International Conference on SMiRT, Porto Alegre, Brazil, August, 1995
  8. W. K. In, D. S. Oh, T. H. Chun and Y. H. Jung, 'Numerical Examination of Coolant Flow Mixing in Nuclear Fuel Assembly with Mixing Promoters', 8th Int. Conference on Nuclear Engineering, Baltimore, USA, April 2-6 (2000)
  9. W. K. In, 'Numerical Study of Coolant Mixing Caused by the Flow Deflectors in a Nuclear Fuel Bundle,' Nuclear Technology, 134 (2), 187(2001)
  10. CFX International, CFX-4.2: Solver, AEA Technology, Oxfordshire, UK (1997)
  11. B. E. Launder and D. B. Spalding, 'The Numerical Computation of Turbulent Flows,' Computational Methods in Applied Mechanics and Engineering, 3, 269 (1974) https://doi.org/10.1016/0045-7825(74)90029-2