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CFD Analysis of Localised Crud Effects on the Flow of Coolant in Nuclear Rod Bundles

机译:CFD分析局部Crud对核棒束冷却剂流动的影响

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摘要

It has been suggested that crud deposits on a number of adjacent fuel rods might reduce coolant flow rates in associated sub-channels. Such reduced flow rates could then worsen thermal-hydraulic conditions, such as margin to saturated boiling, fuel surface temperature, and the DNB ratio. We report the results of a detailed computational fluid dynamics study of the flow pattern in a partially-crudded rod bundle. Values obviously depend on, for example, the thickness of crud assumed, but sub-channel flow rate reductions of ~10% were predicted by this analysis. However, this mass flow rate reduction was found to be more than offset by improved heat transfer induced by the relatively rough surface of the crud. Cladding temperatures were predicted to be essentially unchanged, and the DNBR was similarly little altered. We conclude that such flow reduction and diversion is not likely to be of concern.
机译:已经提出,在许多相邻的燃料棒上的沉淀物沉积物可能会降低相关联的子通道中的冷却剂流速。这样降低的流速可能会使热工条件恶化,例如饱和沸腾裕度,燃料表面温度和DNB比。我们报告了部分压碎的棒束中流型的详细计算流体动力学研究的结果。该值显然取决于,例如,假定的粗料厚度,但是通过该分析,可以预测约10%的子通道流速降低。然而,发现这种质量流率的降低远远超过了由相对粗糙的表面引起的热传递的改善。预测包层温度基本不变,并且DNBR几乎没有变化。我们得出的结论是,这种流量减少和转移不太可能引起关注。

著录项

  • 作者

    Cinosi, N; Walker, SP;

  • 作者单位
  • 年度 2015
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  • 入库时间 2022-08-20 21:06:54

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