首页> 外文期刊>Transactions of the American nuclear society >Validation of COBRA-TF Critical Heat Flux Predictions for a Small Hydraulic Diameter Geometry Under Natural Boiling Conditions
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Validation of COBRA-TF Critical Heat Flux Predictions for a Small Hydraulic Diameter Geometry Under Natural Boiling Conditions

机译:自然沸腾条件下小水力直径几何的COBRA-TF临界热通量预测的验证

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摘要

The calculated results are in good agreement with the experimental data, with respect to CHF values, the trend of the CHF with diameter/length ratio and the oscillatory flow behavior. It is shown that COBRA-TF calculates conservative CHF values for small hydraulic geometry in the natural circulation boiling case.
机译:关于CHF值,CHF随直径/长度比的变化趋势和振荡流动特性,计算结果与实验数据非常吻合。结果表明,在自然循环沸腾情况下,COBRA-TF可为较小的水力几何计算保守的CHF值。

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