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Measurement of Interfacial Structures in Horizontal Air-Water Bubbly Flows

机译:水平气泡水流中界面结构的测量

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In order to predict multi-dimensional phenomena in nuclear reactor systems, methods relying on computational fluid dynamics (CFD) codes are essential. However, to be applicable in assessing thermal-hydraulic safety, these codes must be able to accurately predict the development of two-phase flows. Therefore, before practical application these codes must be assessed using experimental databases that capture multi-dimensional phenomena. While a large database exists that can be employed to assess predictions in vertical flows, the available database for horizontal flows is significantly lacking. Therefore, the current work seeks to develop an additional database in air-water horizontal bubbly flow through a 38.1 mm ID test section with a total development length of approximately 250 diameters. The experimental conditions are chosen to cover a wide range of the bubbly flow regime based upon flow visualization using a high-speed video camera. A database of local time-averaged void fraction, bubble velocity, interfacial area concentration, and bubble Sauter mean diameter are acquired throughout the pipe cross-section using a four-sensor conductivity probe. To investigate the evolution of the flow, measurements are made at axial locations of 44, 116, and 244 diameters downstream of the inlet. In the current work, only measurements obtained at L/D = 244 are presented. It is found that increasing the liquid superficial velocity tends to reduce both the bubble size and the degree of bubble packing near the upper wall. However, it is observed that the position of the maximum void fraction value remains nearly constant and is located approximately one bubble diameter away from the upper wall. It is also found that the bubble velocity exhibits a power law behavior resembling a single phase liquid turbulent velocity profile. Moreover, the local bubble velocity tends to decrease as the local void fraction increases. Conversely, increasing the gas superficial velocity is found to have little effect on the bubble size or velocity, but increases the bubble packing near the upper pipe wall.
机译:为了预测核反应堆系统中的多维现象,依赖于计算流体动力学(CFD)代码的方法必不可少。但是,为了适用于评估热工安全性,这些规范必须能够准确预测两相流的发展。因此,在实际应用之前,必须使用捕获多维现象的实验数据库对这些代码进行评估。尽管存在可以用来评估垂直流预测的大型数据库,但水平流的可用数据库却十分缺乏。因此,当前的工作是寻求开发一个通过38.1 mm内径测试段的空气-水水平气泡流的附加数据库,其总开发长度约为250个直径。基于使用高速摄像机的流动可视化,选择实验条件以覆盖大范围的气泡流动状态。使用四传感器电导率探头在整个管道横截面中获取本地时间平均空隙率,气泡速度,界面面积浓度和气泡Sauter平均直径的数据库。为了研究流量的演变,在进口下游的轴向直径分别为44、116和244的位置进行了测量。在当前工作中,仅显示了在L / D = 244时获得的测量结果。发现增加液体表面速度趋向于减小气泡尺寸和靠近上壁的气泡堆积程度。然而,观察到最大空隙率值的位置几乎保持恒定,并且位于距上壁约一个气泡直径的位置。还发现气泡速度表现出类似于单相液体湍流速度分布的幂律行为。此外,随着局部空隙率的增加,局部气泡速度趋于降低。相反,发现增加气体表观速度对气泡大小或速度几乎没有影响,但增加了上管壁附近的气泡堆积。

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