首页> 外文期刊>Nuclear science and engineering >On the Wall Drag Term in the Averaged Momentum Equation for Dispersed Flows
【24h】

On the Wall Drag Term in the Averaged Momentum Equation for Dispersed Flows

机译:关于分散流的平均动量方程中的壁阻力项

获取原文
获取原文并翻译 | 示例
       

摘要

When fluid particles such as bubbles and droplets are not in contact with the wall, one probably neglects the wall drag term in the one-dimensional momentum equation for the dispersed phase. This treatment however leads to an unphysical prediction of the motion of the dispersed phase. In the framework of the conventional two-fluid model, how to apply the wall drag to the dispersed phase is disputable. The interface force acting on a fluid particle results from the interaction between the fluid particle and the surrounding continuous fluid. To clarify the contributions to the forces acting on the dispersed phase, the volume-averaged momentum equations are formulated based on the equation of a single fluid particle motion. After that, one-dimensional momentum equations are newly obtained from the averaged equations. It is shown that the wall drag term in the dispersed phase is associated with the spatial gradient of the volume-averaged viscous stress of the continuous phase. The magnitude of the wall drag term for a phase is its volume fraction multiplied by the total two-phase pressure drop induced by the wall shear of the continuous phase.
机译:当诸如气泡和液滴之类的流体粒子不与壁接触时,在分散相的一维动量方程中,人们可能会忽略壁的阻力项。然而,这种处理导致对分散相运动的非物理预测。在常规的双流体模型的框架中,如何将壁阻力施加到分散相上是有争议的。作用在流体颗粒上的界面力是由流体颗粒与周围连续流体之间的相互作用产生的。为了阐明对作用在分散相上的力的贡献,基于单个流体粒子运动的方程式建立了体积平均动量方程式。之后,从平均方程重新获得一维动量方程。结果表明,分散相中的壁阻力项与连续相的体积平均粘滞应力的空间梯度有关。相的壁阻力项的大小是其体积分数乘以连续相的壁剪切引起的总两相压降。

著录项

  • 来源
    《Nuclear science and engineering》 |2014年第2期|225-239|共15页
  • 作者单位

    Korea Atomic Energy Research Institute, Thermal-Hydraulic Safety Research Division 373-1 Dukjin-dong, Yuseong-gu, Daejeon, 305-701, Korea;

    Seoul National University of Science and Technology, Department of Mechanical System Design Engineering 232 Gongneung-ro, Nowon-gu, Seoul, 139-743, Korea;

    Korea Atomic Energy Research Institute, Thermal-Hydraulic Safety Research Division 373-1 Dukjin-dong, Yuseong-gu, Daejeon, 305-701, Korea;

  • 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
  • 中图分类
  • 关键词

  • 入库时间 2022-08-18 00:42:57

相似文献

  • 外文文献
  • 中文文献
  • 专利
获取原文

客服邮箱:kefu@zhangqiaokeyan.com

京公网安备:11010802029741号 ICP备案号:京ICP备15016152号-6 六维联合信息科技 (北京) 有限公司©版权所有
  • 客服微信

  • 服务号