Numerical simulation of hydraulic characteristics of coolant in rod spacer grids
Thermal hydraulic performance analysis of fuel rod bundle with spacer grids takes important role among the pressure water reactor (PWR) design and safety operation. Due to its intrinsic complex geometric configuration, previous studies were almost based on one-dimensional code and many simplifications had to be made to make simulations manageable. In the present paper, the intact and simplified spacer grids were simulated and analyzed by using the Computational Fluid Dynamic (CFD) software, and efforts were emphasized on the influence factors on the flow field including spacer grids with mixing vanes only and spacer grids with mixing vanes springs and dimples, respectively. The results indicate that the springs and dimples have great influences on the flow field and thus cannot be neglected during numerical simulation of coolant flow through subchannels with spacer grids. The transverse flows and pressure drop with springs and dimples show more intense than those without spacer and dimples as expected.
CFD, Fuel rod bundle Reactor Spacer grids Thermal hydraulics
Ma Teng-da ZENG He-yi GUO Yun
College of Nuclear Science and Technology, Harbin Engineering University, P.R.China, 150001
国际会议
哈尔滨
英文
576-581
2011-11-24（万方平台首次上网日期，不代表论文的发表时间）