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Two-phase flow interfacial structures in a rod bundle geometry .

机译:棒束几何中的两相流界面结构。

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摘要

Interfacial structure of air-water two-phase flow in a scaled nuclear reactor rod bundle geometry was studied in this research. Global and local flow regimes were obtained for the rod bundle geometry. Local two-phase flow parameters were measured at various axial locations in order to understand the transport of interfacial structures. A one-dimensional two-group interfacial area transport model was evaluated using the local parameter database.;Air-water two-phase flow experiments were performed in an 8 X 8 rod bundle test section to obtain flow regime maps at various axial locations. Area averaged void fraction was measured using parallel plate type impedance void meters. The cumulative probability distribution functions of the signals from the impedance void meters were used along with a self organizing neural network to identify flow regimes. Local flow regime maps revealed the cross-sectional distribution of flow regimes in the bundle.;Local parameters that characterize interfacial structure, that is, void fraction alpha, interfacial area concentration, ai, bubble Sauter mean diameter, DSm and bubble velocity, vg were measured using four sensor conductivity probe technique. The local data revealed the distribution of the interfacial structure in the radial direction, as well as its development in the axial direction. In addition to this, the effect of spacer grid on the flow structure at different gas and liquid velocities was revealed by local parameter measurements across the spacer grids.;A two-group interfacial area transport equation (IATE) specific to rod bundle geometry was derived. The derivation of two-group IATE required certain assumption on the bubble shapes in the subchannels and the bubbles spanning more than a subchannel. It was found that the geometrical relationship between the volume and the area of a cap bubble distorted by rods was similar to the one derived for a confined channel under a specific geometrical transformation.;The one dimensional form of the interfacial area transport equation was evaluated against the one dimensional area averaged data obtained in the rod bundle. The model was evaluated for the overall development of the flow structure. The effect of spacer grid was not considered in the model evaluation scheme, in view of the observation from flow regime identification, that the flow structure developed within a short distance downstream of the spacer grid. The evaluation results showed that one-group interfacial area transport model agreed well with the experimental data. However, the two-group model prediction deviate from the experimental data. The model predicted experimental data within 30% for flow conditions with lower liquid flow rates. The model needs further developments for it to be applicable to a wide range of flow conditions.
机译:本研究研究了比例核反应堆棒束几何结构中气水两相流的界面结构。获得了棒束几何的整体和局部流态。为了了解界面结构的传输,在各个轴向位置测量了局部两相流参数。使用局部参数数据库评估了一维两类界面区域的运输模型。在8 X 8棒束试验段中进行了空气-水两相流动实验,以获得各个轴向位置的流动状态图。使用平行板型阻抗空隙计测量面积平均空隙率。来自阻抗空隙计的信号的累积概率分布函数与自组织神经网络一起用于识别流动状态。局部流态图显示了束中流态的横截面分布。表征界面结构的局部参数,即空隙率α,界面面积浓度,ai,气泡Sauter平均直径,DSm和气泡速度vg为使用四传感器电导率探针技术进行测量。局部数据揭示了界面结构在径向上的分布以及在轴向上的发展。除此之外,还通过跨隔栅的局部参数测量揭示了隔栅在不同气体和液体速度下对流动结构的影响。推导了针对棒束几何形状的两组界面面积传输方程(IATE) 。两组IATE的推导需要对子通道中的气泡形状以及跨越一个子通道的气泡进行一定的假设。发现在特定的几何变换下,杆变形的帽泡的体积与面积之间的几何关系与在有限的几何变换下导出的密闭通道的几何关系相似;评估了界面面积输运方程的一维形式棒束中获得的一维面积平均数据。评估了该模型的流动结构的整体发展。鉴于从流动状态识别的观察,在模型评估方案中未考虑间隔栅网的影响,即流动结构在间隔栅网下游的短距离内发展。评价结果表明,一组界面传输模型与实验数据吻合良好。但是,两组模型的预测与实验数据有所不同。对于液体流速较低的流动条件,该模型预测的实验数据在30%以内。该模型需要进一步开发,以使其适用于各种流动条件。

著录项

  • 作者

    Paranjape, Sidharth S.;

  • 作者单位

    Purdue University.;

  • 授予单位 Purdue University.;
  • 学科 Engineering Nuclear.
  • 学位 Ph.D.
  • 年度 2009
  • 页码 186 p.
  • 总页数 186
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

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