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Experimental investigation of the effects of helical wire coils on critical heat flux, boiling heat transfer and two-phase flow patterns in round tubes.

机译:螺旋线圈对临界热通量,沸腾传热和圆管内两相流型的影响的实验研究。

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摘要

Experimental studies of critical heat flux (CHF), boiling heat transfer and two-phase flow patterns were performed in round tubes in the presence of internal helical wire coils. The data were obtained using the University of Cincinnati's boiling loop and refrigerant 113 as the working fluid.;The experimental CHF tests showed that the CHF in ribbed tubes is significantly above that in smooth tubes over most of the range of interest. The CHF enhancement does not begin until liquid flow rates exceed those at which bubbly-core flow (onset of swirl) is observed. An empirical correlation of the ratio of CHF in helically ribbed tubes to that in straight tubes was developed. Extrapolation of this correlation was consistent with the limited CHF data for tight-pitch coils in the literature. Both the literature data, and the empirical CHF correlation, show that the power required to achieve very high CHF values with tight-pitch wire coils is substantially lower than that needed using smooth tubes or tubes containing twisted tapes.;The flow patterns observed in horizontal flow were essentially similar to those previously observed with air-water. Modification of the flow pattern transition correlations which had been developed for air-water flow were able to predict nearly all of the refrigerant flow pattern transitions in horizontal lines. However, the flow pattern observations in vertical lines showed the presence of a new flow pattern, designated bubbly-core flow. Here the was swirling liquid flow around the tube perimeter and a central (non-swirling) bubbly region. In contrast to earlier tests of boiling heat transfer in tubes with twisted tapes, boiling heat transfer coefficients were not increased over those seen in smooth tubes. A slight modification of the boiling suppression correlation of Gungor and Winterton (58) provided a conservative prediction of the observed heat transfer coefficients.
机译:在圆形螺旋管中,在内部螺旋线圈的情况下,进行了临界热通量(CHF),沸腾传热和两相流型的实验研究。数据是使用辛辛那提大学的沸腾回路和制冷剂113作为工作流体而获得的。实验性CHF测试表明,在感兴趣的大多数范围内,带肋管的CHF显着高于光滑管的CHF。直到液体流速超过观察到气泡芯流(涡旋开始)的流速,CHF才开始增强。建立了螺旋肋管中的CHF与直管中的CHF的经验关系。这种相关性的外推法与文献中有限间距线圈的有限CHF数据一致。文献数据和经验CHF相关性均表明,使用紧密间距的线圈实现非常高的CHF值所需的功率显着低于使用光滑管或包含扭曲带的管所需的功率。流量基本上类似于以前用空气-水观察到的流量。已经针对空气-水流开发的流型转变相关性的修改能够预测几乎所有水平线中的制冷剂流型转变。但是,在垂直线上观察到的流型表明存在新的流型,称为泡芯流。在此,绕管周缘和中央(非旋流)气泡区周围的液体呈回旋状。与较早在带有扭曲带的管中进行沸腾传热的测试相反,沸腾传热系数并未比在光滑管中看到的增加。对Gungor和Winterton(58)的沸腾抑制相关性的轻微修改,为观察到的传热系数提供了保守的预测。

著录项

  • 作者

    Lan, Jianwei.;

  • 作者单位

    University of Cincinnati.;

  • 授予单位 University of Cincinnati.;
  • 学科 Engineering Mechanical.;Engineering Nuclear.
  • 学位 Ph.D.
  • 年度 1996
  • 页码 268 p.
  • 总页数 268
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

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