SHAPE OPTIMIZATION OF A Y-MIXING VANE IN NUCLEAR FUEL ASSEMBLY

핵연료 봉다발내 Y 혼합날개의 형상최적설계

  • Published : 2009.06.30

Abstract

The purposes of present work are to analyze the convective heat transfer with three-dimensional Reynolds-averaged Navier-Stokes analysis, and to optimize shape of the mixing vane taken tolerance into consideration by using the analysis results. Response surface method is employed as an optimization technique. The objective function is defined as a combination of heat transfer rate and inverse of pressure drop. Two bend angles of mixing vane are selected as design variables. Thermal-hydraulic performances have been discussed and optimum shape has been obtained as a function of weighting factor in the objective function. The results show that the optimized geometry improves the heat transfer performance far downstream of the mixing vane.

Keywords

References

  1. 1991, Shen, Y.F., Cao, Z.D. and Lu, Q.G., "An investigation of crossflow mixing effect caused by grid spacer with mixing blades in a rod bundle," Nucl. Engng and Design, Vol.125, pp.111-119 https://doi.org/10.1016/0029-5493(91)90071-O
  2. 1995, Karoutas, Z., Gu, C.Y. and Scholin, B., "3D Flow Analyses for Design of Nuclear Fuel Spacer," Proceedings of The 7th Int. Meeting on Nuclear Reactor Thermal-Hydraulics, New York, USA, pp.3153-3174
  3. 2001, In, W.K., Oh, D.S. and Chun, "Flow analysis for optimum-design of mixing vane in dda PWR fuel assembly," J. of KNS, Vol.33, No.3, pp.327-338
  4. 2003, Cui, X.Z. and Kim, K.Y., "Three-Dimensional Analysis of Turbulent Heat Transfer and Flow Through Mixing Vane in A Subchannel of Nuclear Reactor," Journal of Nuclear Science and Technology, Vol.40, No.10, pp.719-724 https://doi.org/10.3327/jnst.40.719
  5. 2002, Kim, Y.H. and Kim, K.T., "Advanced Spacer Grid Design for the PLUS7 Fuel Assembly," Third Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS3), Kyeongju, pp.493-499
  6. 2005, Kim, K.Y. and Seo, J.W., "Numerical Optimization for The Design of A Spacer Grid with Mixing Vanes in A Pressurized Water Reactor Fuel Assembly," Nuclear Technology, Vol.149, No.1, pp.62-70 https://doi.org/10.13182/NT05-A3579
  7. 2000, In, W.K., Oh, D.S. and Chun, T.H., "Optimization of Flow Directing Vane in a Nuclear Fuel Rod Bundle by CFD Method," Proceedings of The First National Congress on Fluids Engineering, Muju, Korea, pp.467-470
  8. 2007, 신창환, 추연준, 문상기, 천세영, 전태현, "핵연료집합체 지지격자의 혼합날개 형상이 임계열유속에 미치는 영향," 대한기계학회 2007년 춘계학술대회 논문집, pp.2396-2401
  9. 2007, Lee, C.M. and Choi, Y.D., "Comparison of thermo-hydraulic performances of large scale vortex flow (LSVF) and small scale vortex flow (SSVF) mixing vanes in 17x17 nuclear rod bundle," Nuclear engineering and design, Vol.237, No.24, pp.2322-2331 https://doi.org/10.1016/j.nucengdes.2007.04.011
  10. 2008, Nematollahi, M.R. and Nazifi, M., "Enhancement of heat transfer in a typical pressurized water reactor by different mixing vanes on spacer grids," Energy conversion and management, Vol.49, No.7, pp.1981-1988 https://doi.org/10.1016/j.enconman.2007.12.016
  11. 2006, 안정수, 최영돈, "핵연료 집합체에서의 대형 이차와류 혼합날개의 난류생성 특성에 관한 연구," 설비공학 논문집, 제18권, 제10호, pp.811-818
  12. 2006, CFX-11.0 Solver Theory, Ansys inc
  13. 2001, Menter, F. and Esch, T., "Elements of industrial heat transfer prediction", 16th Bazilian Congress of Mechanical Engineering(COBEM), Uberlandia, Brazil, 2001
  14. 2001, Shyy, W., Papila, N., Vaidyanathan, R. and Tucker, K., Progress in Aerospace Science, Vol.37, pp.59-118 https://doi.org/10.1016/S0376-0421(01)00002-1