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Drift-flux correlation for rod bundle geometries

机译:棒束几何形状的流通量相关性

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摘要

A new drift-flux correlation has been developed to predict void fraction over a wide range of two-phase flow conditions in rod bundle geometries. An experimental database that represents low liquid flow and low pressure conditions in a scaled 8 × 8 rod bundle test facility is emphasized for this work. At these conditions, recirculating flow patterns may affect two-phase flow characteristics. Such effects may not be appropriately considered in earlier rod bundle correlations for drift velocity and distribution parameter. In the current approach, an existing drift-flux correlation that accounts for the effect of recirculating flow as two-phase flow regimes transition from bubbly to cap-bubbly flow is incorporated to determine distribution parameter. A performance analysis demonstrates that the proposed correlation improves upon existing correlations with an average relative error of ±4.5% when predicting the database utilized for in this work. The new correlation is also demonstrated to scale appropriately to prototypic plant conditions.
机译:已经开发了一种新的漂移-通量相关性,以预测棒束几何中两相流条件下的空隙率。这项工作着重于在比例为8×8的棒束测试设备中代表低液体流量和低压条件的实验数据库。在这些条件下,再循环流型可能会影响两相流特性。对于漂移速度和分布参数,在较早的棒束相关中可能没有适当考虑这种影响。在当前方法中,结合了现有的漂移-通量相关性,该相关性考虑了两相流态从气泡流向帽泡流过渡时再循环流的影响,以确定分布参数。性能分析表明,当预测用于此工作的数据库时,所提出的相关性会改善现有的相关性,平均相对误差为±4.5%。还证明了新的相关性可以根据原型植物条件适当缩放。

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  • 作者单位

    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;

    Institute of Nuclear Engineering and Science, National Tsing Hua University, No. 101, Section 2, Kuang-Fu Road, Hsinchu 30013, People's Republic of China;

    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;

    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;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);
  • 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; Boiling water reactor;

    机译:棒束两相流;空隙率;漂流沸水反应堆;

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