CFD evaluation of turbulence model on heat transfer in 5×5 rod bundles

被引:0
作者
Chao, Yan-Meng [1 ]
Yang, Li-Xin [1 ]
Zhang, Yu-Xiang [2 ]
Pang, Zheng-Zheng [2 ]
机构
[1] School of Mechanical, Electronic and Control Engineering, Beijing Jiaotong University, Beijing
[2] China Nuclear Power Technology Research Institute, Shenzhen
来源
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | 2014年 / 48卷 / 10期
关键词
CFD; Spacer grid; Thermal-hydraulic; Turbulence model;
D O I
10.7538/yzk.2014.48.10.1782
中图分类号
学科分类号
摘要
Different turbulence models may lead to different results when analyzing fuel assemblies using computational fluid dynamics (CFD) method. In this paper, a 5×5 rod bundle model was built to analyze the relationship between flow and heat transfer. The pressure drop and Nu were calculated using ANSYS CFX. Three factors evaluating swirling flow and cross-flow were used to analyze the inner relationship between flow field and heat transfer. The performances of various turbulence models, including eddy viscosity model and Reynold stress model, were evaluated. The comparison between numerical and similar experimental results indicates that Reynold stress model is more appropriate for modeling flow features and heat transfer in spacer grids discussed in this paper. ©, 2014, Yuanzineng Kexue Jishu/Atomic Energy Science and Technology. All right reserved.
引用
收藏
页码:1782 / 1789
页数:7
相关论文
共 10 条
  • [1] Lee K.B., Jang H.G., A numerical prediction on the turbulent flow in closely spaced bare rod arrays by a nonlinear k-ε model, Nuclear Engineering and Design, 172, pp. 351-357, (1997)
  • [2] Smith L.D., Conner M.E., Liu B., Et al., Benchmarking computational fluid dynamics for application to PWR fuel, Proceedings of the 10th International Conference on Nuclear Engineering, pp. 823-830, (2002)
  • [3] Yadigaroglu G., Anderani M., Dreier J., Et al., Trends and needs in experimentation and numerical simulation for LWR safety, Nuclear Engineering and Design, 221, pp. 205-223, (2003)
  • [4] Liu C.C., Ferng Y.M., Shih C.K., CFD evaluation of turbulence models for flow simulation of the fuel rod bundle with a spacer assembly, Applied Thermal Engineering, 40, pp. 389-396, (2012)
  • [5] Holloway M.V., McClusky H.L., Beasley D.E., Et al., The effect of support grid features on local, single-phase heat transfer measurements in rod bundles, ASME Journal of Heat Transfer, 126, pp. 43-53, (2004)
  • [6] Holloway M.V., Conover T.A., McClusky H.L., Et al., The effect of support grid design on azimuthal variation in heat transfer coefficient for rod bundles, ASME Journal of Heat Transfer, 127, pp. 598-605, (2005)
  • [7] Cui X.Z., 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, 40, 10, pp. 719-724, (2003)
  • [8] Lee C.M., Choi Y.D., Comparison of thermo-hydraulic performances of large scale vortex flow (LSVF) and small scale vortex flow (SSVF) mixing vanes in 17×17 nuclear rod bundle, Nuclear Engineering and Design, 237, 24, pp. 2322-2331, (2007)
  • [9] In W.K., Chun T.H., Oh D.S., Et al., CFD analysis of turbulent flows in rod bundles for nuclear fuel spacer design, Transactions of the 15th International Conference on Structural Mechanics in Reactor Technology, pp. 365-372, (1999)
  • [10] In W.K., Chun T.H., Shin C.H., Et al., Numerical computation of heat transfer enhancement of a PWR rod bundle with mixing vane spacers, Nuclear Technology, 161, 1, pp. 69-79, (2008)