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Modelling and computation of cavitation and boiling bubbly flows with the NEPTUNE_CFD code

机译:使用NEPTUNE_CFD代码对空化和沸腾气泡流进行建模和计算

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This paper focuses on the modelling and the numerical simulation with the NEPTUNE_CFD code of cavitation phenomena and boiling bubbly flows. Compressible, unsteady, turbulent 3D two-phase flow is computed by the NEPTUNE_CFD solver, developed jointly by EDF R&D and CEA. The numerical approach is based on a finite-volume co-located cell-centred approach and makes use of an original pressure-based multi-field coupling algorithm [Mechitoua, N., et al., 2003. An unstructured finite volume solver for two-phase water/vapour flows modelling based on an elliptic oriented fractional step method. In: Proceedings of the 10th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH 10), Seoul, Korea]. The cavitation nuclei come from wall nucleation or are pre-existing in the flow. Generated vapor bubbles are advected by the flow and expand in the regions where the local pressure is below the saturation with a tendency to agglomerate into slug bubbles. The model predictions compared with experimental data on enough selective local variables showed that satisfactory agreement could be obtained without any floating parameter to fit the data. The second part of the paper deals with boiling bubbly flow through a mixing device representing the effect of a fuel assembly spacer grid equipped with mixing blades (DEBORA-mixing experiment, CEA, Grenoble). Local measurements of the void fraction are provided downstream the mixing enhancer. The computations compare favourably with the experimental results; in particular, the global effect of the mixing blades was observed. A modification of the classical nucleate boiling model is proposed to overcome the strong model sensitivity with respect to near wall grid refinement.
机译:本文着重于利用空化现象和沸腾气泡流的NEPTUNE_CFD代码进行建模和数值模拟。由EDF R&D和CEA联合开发的NEPTUNE_CFD求解器计算可压缩,不稳定,湍流的3D两相流。数值方法基于有限体积的共处单元为中心的方法,并使用了基于压力的原始多场耦合算法[Mechitoua,N.,et al。,2003。非结构化有限体积求解器椭圆定向分数步法的水/蒸气两相流模型。在:第十届国际核反应堆热工水力专题会议论文集(NURETH 10),韩国首尔]。空化核来自壁成核或已预先存在于流中。所产生的蒸气气泡通过流动被平流,并在局部压力低于饱和压力的区域中膨胀,并趋于聚集成团状气泡。模型预测与足够的选择性局部变量的实验数据相比较表明,无需任何浮动参数即可拟合出令人满意的一致性。本文的第二部分涉及通过混合装置的沸腾气泡流,该混合装置代表配备有混合叶片的燃料组件隔板的作用(DEBORA混合实验,CEA,格勒诺布尔)。空隙率的局部测量值在混合增强剂的下游提供。计算结果与实验结果相吻合。特别地,观察到混合叶片的整体效果。提出了对经典核沸腾模型的修改,以克服关于近壁网格细化的强大模型敏感性。

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