壁面受热圆柱管内恶化湍流传热的建模与仿真

IF 0.5 Q4 ENGINEERING, MECHANICAL
P. Vegendla, R. Hu
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引用次数: 0

摘要

本文讨论了气冷核动力反应堆在压力传导冷却(PCC)过程中由于力循环流动损失而引起的壁面加热流体流动的恶化湍流传热(DTHT)的建模和模拟。DTHT状态被定义为由于加速度和浮力的增加而导致正常湍流热输运的恶化。Nek5000和STAR-CCM+等计算流体动力学(CFD)工具可以帮助分析反应器中的DTHT现象,从而实现高效的热流体设计。在壁面加热圆管内进行了三维CFD非等温建模和模拟。利用Nek5000和STAR-CCM+两种CFD工具对模拟结果进行了验证,并用实验数据进行了验证。正如预期的那样,两种CFD工具预测的体积温度是相同的。利用Nek5000对沿管轴方向的壁面温度进行了模拟计算,结果与实测数据吻合较好。在STAR-CCM+中,壁面温度低于预期主要是由于壁面区域湍流较大。在STAR-CCM+中,与进口换热值相比,出口预测的DTHT超过48%。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Modeling and Simulations of Deteriorated Turbulent Heat Transfer in Wall-Heated Cylindrical Tube
This paper discusses the modeling and simulations of deteriorated turbulent heat transfer (DTHT) for a wall-heated fluid flows, which can be observed in gas-cooled nuclear power reactors during pressurized conduction cooldown (PCC) event due to loss of force circulation flow. The DTHT regime is defined as the deterioration of normal turbulent heat transport due to increase of acceleration and buoyancy forces. The computational fluid dynamics (CFD) tools such as Nek5000 and STAR-CCM+ can help to analyze the DTHT phenomena in reactors for efficient thermal-fluid designs. Three-dimensional (3D) CFD nonisothermal modeling and simulations were performed in a wall-heated circular tube. The simulation results were validated with two different CFD tools, Nek5000 and STAR-CCM+, and validated with an experimental data. The predicted bulk temperatures were identical in both CFD tools, as expected. Good agreement between simulated results and measured data were obtained for wall temperatures along the tube axis using Nek5000. In STAR-CCM+, the under-predicted wall temperatures were mainly due to higher turbulence in the wall region. In STAR-CCM+, the predicted DTHT was over 48% at outlet when compared to inlet heat transfer values.
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来源期刊
CiteScore
1.60
自引率
16.70%
发文量
12
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