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DRIFT-FLUX CORRELATION FOR A ROD BUNDLE GEOMETRY

机译:杆束几何的漂移通量相关

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摘要

A rod bundle drift-flux correlation is developed with intended application across a wide range of two-phase flow conditions. Special consideration is made for fluid flow mechanisms at low liquid velocity and low pressure conditions. In these instances, gravitational forces from the density difference of the associated fluid phases are more significant. Secondary flow patterns may develop as a result and a drift-flux correlation would need to make appropriate adjustments. Earlier correlations may have increased error at these conditions if they have been formulated with respect to relatively higher pressure or flow rate. In the present work, area-average void fraction data at low liquid velocity and low pressure conditions is considered. This data was collected from an adiabatic 8×8 rod bundle test facility. Superficial liquid velocity ranged from 0 to 1.0 m/s and superficial gas velocity ranged from 0.030 to 10.0 m/s. A distribution parameter correlation is developed with respect to this data, an existing drift velocity correlation, and the kinematic constitutive relation of the drift-flux model. Initial analysis of the new correlation demonstrates more appropriate gas velocity calculations than earlier correlations. The drift velocity and distribution parameter dependence on void fraction is also shown in order to demonstrate any physical inconsistencies. Overall, considering the effects of secondary flow patterns may warrant a drift flux correlation as more appropriate in low pressure and low liquid velocity conditions.
机译:棒束漂移-通量相关性的开发是针对广泛的两相流条件下的预期应用。对于低液体速度和低压条件下的流体流动机理要特别考虑。在这些情况下,来自相关流体相的密度差的重力更为显着。结果可能会形成二次流模式,并且需要对流量-流量相关性进行适当的调整。如果已针对相对较高的压力或流速制定了较早的相关性,则在这些条件下的误差可能会增加。在目前的工作中,考虑了低液体速度和低压条件下的面积平均空隙率数据。该数据是从绝热的8×8棒束测试设备中收集的。表观液体速度范围为0至1.0 m / s,表观气体速度范围为0.030至10.0 m / s。针对该数据,现有的漂移速度相关性以及漂移-通量模型的运动本构关系,开发了分布参数相关性。新的相关性的初步分析表明,与早期的相关性相比,气体速度计算更为合适。还示出了漂移速度和分布参数对空隙率的依赖性,以证明任何物理上的矛盾。总的来说,考虑到次级流动模式的影响,可以保证在低压和低液速条件下更适合漂移流量的相关性。

著录项

  • 来源
  • 会议地点 Reno NV(US)
  • 作者单位

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

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

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

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

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

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

    Nuclear Fuel Industries Ltd.3135-41 Muramatsu, Tokai-mura, Naka-gun, Ibaraki 311-1196, Japan;

    Institute of Nuclear Safety System, Inc. 64, Sata, Mihama-cho, Mikata-gun, Fukui 919-1205, Japan;

    Institute of Nuclear Safety System, Inc. 64, Sata, Mihama-cho, Mikata-gun, Fukui 919-1205, Japan;

  • 会议组织
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    rod bundle; two-phase flow; void fraction; drift-flux model; boiling water reactor;

    机译:棒束两相流空隙率漂移通量模型沸水反应堆;
  • 入库时间 2022-08-26 13:47:38

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