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논문 상세정보

핵연료 집합체에서의 대형 이차 와류 혼합날개의 난류생성 특성에 관한 연구

A Study of Turbulence Generation Characteristics of Large Scale Vortex Flow Mixing Vane of Nuclear Fuel Rod Bundle

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 the 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 $35D_h$ after the spacer grid. The streamwise vorticity generated by LSVF sustain two times more than that split mixing vane.

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참고문헌 (11)

  1. Rowe, D. S., Johnson, B. M. and Knudsen, J. G., 1974, Implications concerning rod bundle cross flow mixing based on measurements of turbulent flow structure, Int. J. Heat Mass Transfer, 17, pp.407-419 
  2. An, J. S. and Choi, Y. D., 2004, A Study of Turbulence Characteristics of Large Scale Vortex Flow Mixing Vane of Nuclear Fuel Rod Bundle, Proceeding of KSME Spring Annal Meeting 
  3. Ibragimov, M. K., Isupov, I. V., Kobzar, L. L. and Subbotin, V. I., 1966, Calculation of the tangential stresses at the wall in a channel and the velocity distribution in a turbulent flow of liquid, Atomic Energy 21, pp. 731-739 
  4. Shen, Y. F., Cao, Z. D. and Lu, Q. G., 1991, An investigation of crossflow mixing effect caused by grid spacer with mixing blades in a rod bundle, Nucl. Engng and Design 125, pp. 111-119 
  5. KEPCO, 1998, Final Safety Analysis Report For Uljin NPP 3/4, Table 4.4 1, Fig. 4.1 2 
  6. In, W. K., Oh, D. S. and Chun, T. H., 2001, Flow analysis for optimum- design of mixing vane in a PWR fuel assembly, J. of KNS, Vol. 33, No.3, p, 327 
  7. Park, J. S., 2001, A Study of Turbulent Heat Transfer Performance Enhancement in Rod Bundle Subchannel by the Large Scale Secondary Vortex Flow, Ph. D. thesis, The University of Korea, pp. 13-15,64-66 
  8. Rehme, K. and Trippe, G., 1980, Pressure drop and velocity distribution in rod bundle with spacer grids, Nucl. Engng And Design 62, pp. 349-359 
  9. Yang, S. K. and Chung, M. K., 1996, Spacer grid effects on turbulent flow in rod bundles, J. of KNS, Vol. 28, No.1, p. 56 
  10. Karoutas, Z., Gu, C. Y. and SchoIin, B., 1995, 3- D flow analyses for design of nuclear fuel spacer, Proceedings of the NURETH-7 (NUREG/ CP-0142, Vol. 4), pp.3153-3174 
  11. Sha, W. T., 1980, An overview on rodbundle thermal hydraulic analysis, Nucl. Engng and Design 62, pp. 1-24 

이 논문을 인용한 문헌 (3)

  1. Han, Hwa-Taik ; Shin, Dong-Sin ; Choi, Chang-Ho ; Lee, Dae-Young ; Kim, Seo-Young ; Kwon, Yong-Il 2008. "Recent Progress in Air Conditioning and Refrigeration Research: A Review of Papers Published in the Korean Journal of Air-Conditioning and Refrigeration Engineering in 2006" 설비공학논문집 = Korean journal of air-conditioning and refrigeration engineering, 20(6): 427~446 
  2. Jung, S.H. ; Kim, K.Y. ; Kim, K.H. ; Park, S.K. 2009. "SHAPE OPTIMIZATION OF A Y-MIXING VANE IN NUCLEAR FUEL ASSEMBLY" 한국전산유체공학회지 = Journal of computational fluids engineering, 14(2): 1~8 
  3. Jung, Sang-Ho ; Kim, Kwang-Yong 2009. "Shape Optimization of A Twist Mixing Vane in Nuclear Fuel Assembly" 유체기계저널 = Journal of fluid machinery, 12(4): 7~13 

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