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Numerical investigation of turbulent heat transfer and fluid flow in a nuclear fuel plate assembly

机译:核燃料板组件中湍流传热和流体流动的数值研究

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摘要

The flow distribution and heat transfer characteristics in the McMaster nuclear reactor 18-plate nuclear fuel assembly are investigated numerically using a commercial computational fluid dynamics code. The standard k - ε turbulence model together with a two-layer wall boundary model is applied. The code is first validated on a series of problems relevant to the reactor flow. It is then used to predict the flow and heat transfer in the nuclear fuel plate assembly. The predictions are compared to both experimental data and predictions from a one-dimensional thermal hydraulic code.
机译:使用商业计算流体动力学代码对McMaster核反应堆18板核燃料组件中的流动分布和传热特性进行了数值研究。应用标准k-ε湍流模型以及两层壁边界模型。该代码首先针对与反应堆流量相关的一系列问题进行验证。然后将其用于预测核燃料板组件中的流动和传热。将该预测与实验数据和一维热力水力代码的预测进行比较。

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