Calculation of dry out and post-dry out heat transfer in rod bundles using a three field model
Calculation of dry out and post-dry out heat transfer in rod bundles using a three field model
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DOI：
10.1016/j.ijheatmasstransfer.2004.11.005
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发表时间：
2005-04
影响因子：
5.2
通讯作者：
S. Jayanti;M. Valette
中科院分区：
文献类型：
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作者：
S. Jayanti;M. Valette
临界热流密度(CHF)条件是核反应堆燃料棒组件设计和运行中的重要参数。它传统上是使用查找表或经验相关性进行评估的。在本文中，提出了一种一维三场模型形式的关系，它使得高质量CHF的机械预测成为可能，称为干涸。这也允许对干燥后热传递进行更基本的处理。通过将预测与JAERI的TPTF测试系列和ORNL的THTF测试系列的数据进行比较，验证了该关系集的有效性。棒束是以子通道为基础进行建模的。仅考虑隔栅的几何特性，研究了隔栅对流动和换热的影响。在这些试验所考察的参数范围内，即在30-130bar的压力范围内，50-800 kg/m~2s的质量流量范围内，以及从过冷到入口质量为0.89的入口条件下，都能很好地预测棒材的干燥位置和干燥后的温度变化。
The critical heat flux (CHF) condition is an important parameter in the design and operation of nuclear reactor fuel rod assemblies. It has traditionally been evaluated using look-up tables or empirical correlations. In the present paper, a set of relations, in the form of a one-dimensional three-field model, is presented which enables a mechanistic prediction of high-quality CHF known as dry out. This also allows a more fundamental treatment of post-dry out heat transfer. The ensemble of relations is validated by comparing the predictions with data obtained from the TPTF test series of JAERI and the THTF test series of ORNL. The rod bundles have been modelled on a sub-channel basis. The effect of spacer grids on the flow and heat transfer has been studied by including their geometrical characteristics only. Good predictions of the dry out location and the post-dry out variation of the rod temperature are obtained over the range of parameters investigated in these tests, namely, in the pressure range of 30–130bar, mass flux range of 50–800kg/m2s and inlet condition ranging from sub-cooled to an inlet quality of 0.89.