Transactions of the Korean Society of Mechanical Engineers B (대한기계학회논문집B)

The Korean Society of Mechanical Engineers (대한기계학회)
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A Study of Beat Transfer Characteristics of Large Scale Vortex Flow Mixing Vane of Nuclear Fuel Rod Bundle

핵연료집합체에서의 대형이차와류 혼합날개의 열전달 특성에 관한 연구

  • 안정수 (고려대학교 대학원 기계공학과) ;
  • 최영돈 (고려대학교 기계공학과)
  • Published : 2006.01.01
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Abstract

Mixing vanes have been installed in the space grid of nuclear fuel rod bundle to improve turbulent heat transfer. Split mixing vanes induce the vortex flow in the cooling water to swirl in sub-channel of fuel assembly. But, The swirling flow decays rapidly so that the heat transfer enhancing effect limited to short length after the mixing vane. In thi present study, the large scale vortex flow(LSVF) is generated by rearranging the mixing vanes to the coordinated directions. This LSVF mixing vanes generate the most strong secondary flow vortices which maintain about 35 $D_H$ after the spacer grid. The streamwise vorticity generated by LSVF sustain two times more than that split mixing vane. Heat transfer in the rod bundle occurs greatly at the same direction to cross flow, and maximum temperature at the surface of bundle drops about 1.5K

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References

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  1. Thermo-hydraulic characteristics of Hybrid mixing vanes in a 17×17 nuclear rod bundle vol.21, pp.8, 2007, https://doi.org/10.1007/BF03179043