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Numerical Investigation of Single-Phase Heat Transfer in a 2 × 2Rod Bundle with Spacer Grids for a High Pressure Heat Transfer Facility

机译:高压传热装置带隔栅的2×2棒束中单相传热的数值研究

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Numerical simulation has been widely used in nuclear reactor safety analyses to gain insight into key phenomena. This paper compares simulations of a single-phase steady flow in a 2 × 2 rod bundle with spacer grids among different codes based on the high pressure heat transfer facility at University of Wisconsin. The detailed computational fluid dynamics modeling methodology was developed using FLUENT to help in the facility design and pretest analyses. After comparison between different turbulence models, the Standard k-ω was chosen to simulate the effect of unheated solid walls and grid spacers. It was found that solid walls had a small influence on the flow and heat transfer behavior. We note the effect of rod-to-wall gap needs be taken into account if it is larger than half of the gap between the rods. We compared the simulations of FLUENT, COBRA-TF, and TRACE to determine the position of thermocouples to be used in the planned experiments. An investigation was performed on the effect of bending angles of the grid spacer mixing vanes. Results showed that a larger bending angle results in higher turbulence mixing and locally higher Nusselt numbers downstream of the mixing vanes. Also, a small change of the bending angles results in a notable difference in the temperature distributions of the main flow.
机译:数值模拟已广泛用于核反应堆安全分析,以深入了解关键现象。本文基于威斯康星大学的高压传热设备,比较了不同代码中2×2带有间隔栅的棒束中单相稳态流动的模拟。使用FLUENT开发了详细的计算流体动力学建模方法,以帮助进行设施设计和预测试分析。在比较了不同的湍流模型之后,选择了标准k-ω来模拟未加热的实心壁和网格隔板的效果。发现实心壁对流动和传热行为的影响很小。我们注意到,如果杆间壁间隙大于杆间间隙的一半,则需要考虑该影响。我们比较了FLUENT,COBRA-TF和TRACE的仿真,以确定计划实验中要使用的热电偶的位置。对格栅间隔件混合叶片的弯曲角度的影响进行了研究。结果表明,较大的弯曲角度会导致更高的湍流混合,并导致混合叶片下游的局部Nusselt值更高。而且,弯曲角的小变化导致主流的温度分布的显着差异。

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