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首页> 外文期刊>Nuclear Engineering and Design >Investigation of one-dimensional interfacial area transport for vertical upward air-water two-phase flow in an annular channel at elevated pressures
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Investigation of one-dimensional interfacial area transport for vertical upward air-water two-phase flow in an annular channel at elevated pressures

机译:高压下环形通道内垂直向上的空气-水两相流的一维界面区域传输研究

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摘要

The interfacial area transport of vertical, upward, air-water two-phase flows in an annular channel has been investigated at different system pressures. The inner and outer diameters of the annular channel were 19.1 mm and 38.1 mm, respectively. Twenty three inlet flow conditions were selected, which covered bubbly, cap-bubbly, and churn-turbulent flows. These flow conditions also overlapped with twelve conditions of a previous study for comparison. The local flow parameters, such as void fractions, interfacial area concentrations (IAC), and bubble interface velocities, were measured at nine radial positions for the three axial locations and converted into area-averaged parameters. The axial evolutions of local flow structure were interpreted in terms of bubble coalescence, breakup, expansion of the gas-phase due to pressure drop and system pressure. An assessment of interfacial area transport equation (IATE) was made and compared with the experimental data. A discussion of the comparison between model prediction and the experimental results were made.
机译:已经研究了在不同系统压力下垂直,向上,空气-水两相流在环形通道中的界面区域传输。环形通道的内径和外径分别为19.1毫米和38.1毫米。选择了二十三个入口流动条件,包括起泡,盖泡和搅动湍流。这些流动条件也与先前研究的十二个条件进行了比较。在三个轴向位置的九个径向位置测量了局部流动参数,例如空隙率,界面面积浓度(IAC)和气泡界面速度,并将其转换为面积平均参数。用气泡聚结,破裂,由于压降和系统压力引起的气相膨胀来解释局部流动结构的轴向演变。进行了界面面积迁移方程(IATE)的评估,并与实验数据进行了比较。讨论了模型预测与实验结果之间的比较。

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  • 来源
    《Nuclear Engineering and Design》 |2013年第10期|362-379|共18页
  • 作者单位

    School of Nuclear Engineering, Purdue University, 400 Central Drive, West Lafayette, IN 47907-2017, USA,Fauske and Associates, LLC, 16W070 83rd Street, Burr Ridge, IL 60527, USA;

    School of Nuclear Engineering, Purdue University, 400 Central Drive, West Lafayette, IN 47907-2017, USA;

    Korea Atomic Energy Research Institute, 150 Deokjin, Yuseong, Daejeon 305-353, South Korea;

    School of Nuclear Engineering, Purdue University, 400 Central Drive, West Lafayette, IN 47907-2017, USA;

    School of Nuclear Engineering, Purdue University, 400 Central Drive, West Lafayette, IN 47907-2017, USA;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
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