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Pool Boiling Heat Transfer Performance of a Dielectric Fluid With Low Global Warming Potential

机译:低全球变暖潜势的电介质池沸腾传热性能

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摘要

Due to growing concerns over anthropogenic effects on the climate, there is increasing need to replace engineered fluids of high global warming potentials (GWPs), such as hydrofluorocarbons (HFCs) and perfluorocarbons (PFCs), with more environmentally friendly alternatives in thermal management systems. This article presents experimental data and compares various correlations for predicting the pool boiling heat transfer coefficient of a new low-GWP fluid, FK-649. Using a pressurized boiling facility with a smooth aluminum heater, the critical heat flux (CHF) and heat transfer coefficient were measured for the pool boiling of FK-649 at various saturation conditions. The commonly used refrigerant tetrafluoroethane (R-134a) is tested in the same pressurized facility to act as a benchmark for the new fluid. While R-134a exhibited a higher heat transfer coefficient and CHF, this behavior is expected from the fluid properties. Two-phase heat transfer performance of FK-649 is expected to be similar to that of the fluorocarbon FC-72. Experimental data are compared to predictions using the Rohsenow, Borishanskii-Mostinski, Stephan and Abdelsalam, Cooper, and Leiner correlations. Where applicable, empirical constants are obtained by using a least-squares fit to experimental data. The Rohsenow correlation yielded the best result with a new surface-fluid constant C_(s,f) of 0.0037for FK-649.
机译:由于越来越多的人为因素对气候造成影响,因此越来越需要在热管理系统中用更环保的替代品来代替具有高全球变暖潜能值(GWP)的工程流体,例如氢氟碳化合物(HFC)和全氟化碳(PFC)。本文介绍了实验数据,并比较了各种相关性,以预测新型低GWP流体FK-649的池沸腾传热系数。使用带有光滑铝加热器的加压沸腾设备,在各种饱和条件下测量FK-649的池沸腾的临界热通量(CHF)和传热系数。常用的制冷剂四氟乙烷(R-1​​34a)在同一加压设备中进行了测试,以作为新流体的基准。尽管R-134a表现出较高的传热系数和CHF,但从流体特性可以预期这种行为。预计FK-649的两相传热性能与碳氟化合物FC-72相似。使用Rohsenow,Borishanskii-Mostinski,Stephan和Abdelsalam,Cooper和Leiner相关性将实验数据与预测进行比较。在适用的情况下,可通过使用对实验数据的最小二乘拟合获得经验常数。 Rohsenow相关性产生了最佳结果,对于FK-649,新的表面流体常数C_(s,f)为0.0037。

著录项

  • 来源
    《Heat Transfer Engineering》 |2013年第15期|1262-1277|共16页
  • 作者单位

    Department of Nuclear Science & Engineering, Massachusetts Institute of Technology, Cambridge, Massachusetts, USA;

    Nuclear Reactor Laboratory, Massachusetts Institute of Technology, Cambridge, Massachusetts, USA;

    Department of Nuclear Science & Engineering, Massachusetts Institute of Technology, Cambridge, Massachusetts, USA;

    Department of Nuclear Science & Engineering, Massachusetts Institute of Technology, Cambridge, Massachusetts, 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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