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首页> 外文期刊>International Journal of Heat and Mass Transfer >Toward a local drift flux model for high-pressure, subcooled, convective boiling flows
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Toward a local drift flux model for high-pressure, subcooled, convective boiling flows

机译：朝向局部漂移通量模型，用于高压，过冷，对流沸腾流动

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Forced convective boiling is of great interest for several applications in the power and process industry, particularly in nuclear plants. Under certain nominal, incidental or accidental conditions, a boiling crisis may occur resulting in the meltdown of the heating surface. It is then essential to predict as accurately as possible the thermal-hydraulic conditions leading to the occurrence of this boiling crisis. Such an objective cannot reasonably be achieved without a good description of the associated two-phase flow. The objective of the present study is twofold: (1) to identify the necessary key parameters for correctly describing boiling flows, and (2) to present in a didactic way an original stationary and local model involving these parameters. This new model is primarily based on four mixture balance equations, a submodel for the local vapor generation rate, and a turbulence submodel inspired by the pioneering work of [25]. The results obtained with this original boiling flow model are then compared to an extensive experimental data set obtained on a R12/R134a experimental facility. The comparison clearly demonstrates that this new model contains the fewer necessary submodels to describe the structure of a boiling two-phase flow under pressurized water reactor conditions. Subcooled boiling is acceptably described by the model. However, for higher values of void fraction, the model always predicts a nonexistent void fraction peak near the heating wall and overpredicts the wall and liquid temperatures. This behavior may be explained by: (i) the inadequacy of the radial turbulence modeling, (ⅱ) the use of Prandtl's analogy whose validity under boiling conditions is questionable, and (ⅲ) too simplistic a model for the vapor generation rate.
机译：强迫对流沸腾对电力和工艺行业的若干应用感兴趣，特别是在核植物中。在某些标称，偶然或偶然的条件下，可能发生沸腾危机，导致加热表面的崩溃。然后必须尽可能准确地预测热水液态，导致这种沸腾危机的发生。在没有相关的两相流的良好描述，不能合理地实现这种目标。本研究的目的是双重组合：（1）来确定正确描述沸腾流的必要关键参数，（2）以涉及这些参数的原始静止和本地模型以教学方式出现。该新模型主要基于四个混合平衡方程，用于局部蒸汽产生速率的子模型，以及由[25]的开创性工作的启发的湍流子模型。然后将通过该原始沸腾流程模型获得的结果与R12 / R134A实验设施中获得的广泛的实验数据集进行比较。比较清楚地表明，这种新模型含有较少的必要子模型，以描述加压水反应器条件下沸腾两相流的结构。模型可接受的沸腾沸腾。然而，对于空隙率的更高值，模型始终预测加热壁附近的不存在空隙率峰值，并且覆盖壁和液体温度。这种行为可以通过以下方式解释：（i）径向湍流建模的不足，（Ⅱ）使用Prandtl的类比，其在沸腾条件下的有效性是可疑的，并且（Ⅲ）太简单的蒸气产生速率模型。

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