Numerical Investigation to Effect of Spacer Grid on the Subcooled Flow Boiling in Single Rod Channel

被引:0
|
作者
Zhang T. [1 ]
Lü M. [1 ]
Liu H. [1 ]
Zhi C. [1 ]
Chen P. [1 ]
Liu Y. [1 ]
机构
[1] School of Energy and Power Engineering, Xi'an Jiaotong University, Xi'an
关键词
Computational fluid dynamics; Spacer grid; Subcooled boiling; Thermal-hydraulic;
D O I
10.7652/xjtuxb202012014
中图分类号
学科分类号
摘要
To investigate the influence of spacer grid on the thermal-hydraulic characteristics of coolant in fuel rod bundle channel, a single fuel rod and a spacer grid in the center of 5×5 bundle channel are selected for the numerical analysis. Following Eulerian theory, a mathematical model of multiphase flow for the subcooled boiling of coolant in a vertical single rod channel is established. The accuracy of the model is verified by a comparison of numerical simulation results with experiment data. The spatial distribution characteristics of the relevant thermal parameters in the single rod channel with or without spacer grid are obtained, and the influence of spacer grid on the flow and heat transfer characteristics of subcooled boiling is revealed. The results show that compared with the rod channel without spacer grid, the flow field and temperature field rotate anticlockwise in a certain degree after passing through the spacer grid and the mixing wings. The maximum value of the average secondary flow can reach 13.5% of the inlet velocity, and the local secondary flow can reach 60%. The pressure drop of the whole device with spacer grid is only 5% higher than that without spacer grid. The spacer grid can significantly make liquid phase convection heat flux increase, and the maximum increase can reach 44.3%. As a result, the liquid subcooling, wall superheat and vapor volume fraction are further reduced, thus enhancing the safety of nuclear reactor. © 2020, Editorial Office of Journal of Xi'an Jiaotong University. All right reserved.
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页码:116 / 124
页数:8
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