首页> 外文会议>International topical meeting on nuclear reactor thermal hydraulics >RANS SIMULATION OF TURBULENT SWEPT FLOW OVER A WIRE IN A CHANNEL FOR CORE THERMAL HYDRAULIC DESIGN USING K-EPSILON TURBULENCE MODELS
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RANS SIMULATION OF TURBULENT SWEPT FLOW OVER A WIRE IN A CHANNEL FOR CORE THERMAL HYDRAULIC DESIGN USING K-EPSILON TURBULENCE MODELS

机译:基于Kε湍流模型的核心热工水力设计通道中湍流掠过流动的RANS模拟

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This paper presents a thermal hydraulic investigation of a nuclear reactor core, which is one of the most important components in the design of a nuclear power plant. Helical wire-wrapped fuel assemblies have been suggested for coolant mixing, and from a design point of view, an understanding of the influence of the reattachment length and recirculation bubbles could aid in determining the structural parameters for an optimal core thermal hydraulic design. In this study, assessments of Reynolds Averaged Navier-Stokes (RANS) based turbulence models were performed under various flow conditions for a wire in a channel. The calculation results were compared with the DNS results in terms of mean flow analysis and turbulent kinetic energy for further thermal hydraulic design of a wire-wrapped fuel assembly reactor core. The k-epsilon models with a two-layer wall treatment were chosen to predict the turbulent statistics of flow for four cases of a Reynolds equivalent flow rate of 0 to 1,709 along the cross-flow direction and an identical axial flow rate of 5,400. The selected standard k-epsilon models with three different constitutive relationships and a realizable k-epsilon model with the two-layer approach as the turbulence model revealed the locations of flow characteristics of interest, especially recirculation and reattachment, and showed that axial and cross-flow directional velocity profiles are fairly well matched. Relative to the DNS results, the errors in terms of reattachment lengths are approximately 1% for proper turbulence models in each case. From the well-matched flow modeling results and economical computing resources of the k-epsilon model, we conclude that this approach offers sufficient capability as an engineering design tool for core thermal hydraulics.
机译:本文介绍了核反应堆堆芯的热力水力研究,这是核电站设计中最重要的组成部分之一。已经提出了螺旋线绕式燃料组件用于冷却剂混合,并且从设计的角度来看,对重新连接长度和再循环气泡的影响的理解可以帮助确定用于最佳堆芯热工水力设计的结构参数。在这项研究中,基于雷诺平均Navier-Stokes(RANS)湍流模型的评估是在通道中各种导线的流动条件下进行的。将计算结果与DNS结果进行了均流分析和湍动能方面的比较,以用于线绕式燃料组件反应堆堆芯的进一步热力水力设计。选择了经过两层壁处理的kε模型来预测四种情况下的湍流统计,其中沿横向流动方向的雷诺等效流速为0到1,709,相同的轴向流速为5,400。选择的具有三种不同本构关系的标准kε模型和一个以两层方法作为湍流模型的可实现kε模型揭示了感兴趣的流动特性的位置,尤其是再循环和重新附着,并显示了轴向和交叉流动方向的速度曲线非常吻合。相对于DNS结果,在每种情况下,对于合适的湍流模型,在重新连接长度方面的误差约为1%。从匹配良好的流动建模结果和k-ε模型的经济计算资源中,我们得出结论,这种方法提供了足够的能力作为核心热力液压的工程设计工具。

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