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Flow regime, void fraction and interfacial area transport and characteristics of co-current downward two-phase flow

机译:流态,空隙率和界面面积传输以及并流向下两相流的特征

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摘要

Downward two-phase flow is observed in light water reactor accident scenarios such as loss of coolant accident (LOCA) and loss of heat sink accident (LOHS) due to loss of feed water or a secondary pipe break. Hence, a comprehensive literature review has been performed for the co-current downward two-phase flow with information on the flow regime transitions and flow characteristics for each regime in the downward flow. The review compares the experimental data of the flow regime map and the current available transition models. Objectivity of the data varies on the method utilized as a certain degree of subjectivity is still present in the most objective method. Nevertheless, experimental data through subjective methods such as direct visualization or analysis of a wire mesh sensor (WMS) data were still studied in this review. Despite the wide range of flow regime data for numerous pipe sizes, a consensus was not reached for the effect of pipe sizes on flow regime transition. However, it is known that a larger pipe results in greater degree of coalescence at lower gas flow rates (Hibiki et al., 2004).
机译:在轻水反应堆事故场景中观察到向下的两相流,例如由于给水损失或二次管道中断而导致的冷却剂损失事故(LOCA)和散热器事故(LOHS)损失。因此,已经对并流向下两相流进行了全面的文献综述,并获得了有关向下流中每个流态的流态转换和流特性的信息。该评论将流动状态图的实验数据与当前可用的过渡模型进行了比较。数据的客观性因所使用的方法而异,因为在最客观的方法中仍然存在一定程度的主观性。然而,在这篇综述中,仍通过主观方法(例如直接可视化或对金属丝网传感器(WMS)数据进行分析)研究了实验数据。尽管许多管径的流态数据范围广泛,但对于管径对流态过渡的影响尚未达成共识。但是,众所周知,较大的管道​​会在较低的气体流速下产生更大程度的聚结(Hibiki等,2004)。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2016年第10期|39-63|共25页
  • 作者单位

    Purdue Univ, Sch Mech Engn, 585 Purdue Mall, W Lafayette, IN 47907 USA;

    Purdue Univ, Sch Nucl Engn, 400 Cent Dr, W Lafayette, IN 47907 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
  • 中图分类
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