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首页> 外文期刊>Experimental Thermal and Fluid Science: International Journal of Experimental Heat Transfer, Thermodynamics, and Fluid Mechanics >Two-phase flow structure in dual discharges - Stereo PIV measurements
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Two-phase flow structure in dual discharges - Stereo PIV measurements

机译：双放电中的两相流结构-立体声PIV测量

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摘要

The discharge of two-phase flow from a stratified region through single or multiple branches is an important process in many industrial applications including the pumping of fluid from storage tanks, shell-and-tube heat exchangers, and the fluid flow through header to the cooling channels, feeder's tube, of nuclear reactors during loss-of-coolant accidents (LOCA). Knowledge of the flow phenomena involved along with the quality and mass flow rate of the discharging stream(s) is necessary to adequately predict the different phenomena associated with the process. Stereoscopic Particle Image Velocimetry (SPIV) was used to provide detailed measurements of the flow patterns involving distributions of mean velocity, vorticity field, and flow structure. The experimental investigation was carried out to simulate two-phase discharge from a stratified region through branches located on a quarter-circular wall configuration exposed to a stratified gas-liquid environment. The quarter-circular test section is in close dimensional resemblance with that of a CANDU header-feeder system, with branches mounted at orientation angles of zero, 45° and 90° degrees from the horizontal. The experimental data for the phase development (mean velocity, flow structure, etc.) was collected during dual discharge through the horizontal branch and the 45° or 90° branch from an air-water stratified region over two selected Froude numbers in the horizontal branch while maintaining the Froude number in the other branch constant. These measurements were used to describe the effect of outlet flow conditions on phase redistribution in headers and understand the entrainment phenomena.
机译：从分层区域通过单个或多个分支排出两相流是许多工业应用中的重要过程，包括从储罐，管壳式换热器中泵送流体，以及通过集管到冷却器的流体流冷却液损失事故（LOCA）期间核反应堆的通道，馈线管。必须充分了解所涉及的流动现象以及排放流的质量和质量流速，才能充分预测与过程相关的不同现象。立体粒子图像测速（SPIV）用于提供对流型的详细测量，包括平均速度，涡度场和流结构的分布。进行实验研究以模拟从分层区域通过位于暴露于分层气液环境的四分之一圆壁构造上的分支的两相放电。四分之一圆测试部分的尺寸与CANDU集管进纸器系统的尺寸近似，分支安装时与水平方向成零度，45度和90度的定向角。在水平分支中两个选定的弗洛德数上从空气-水分层区域通过水平分支和45°或90°分支的双重排放过程中收集了相发展的实验数据（平均速度，流动结构等）。同时保持另一个分支中的弗洛德数不变。这些测量值用来描述出口流量条件对集管中相重新分布的影响，并了解夹带现象。

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