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首页> 外文期刊>Nuclear Engineering and Design >Experimental heat transfer to supercritical carbon dioxide flowing upward vertical tube with highly conducting surroundings
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Experimental heat transfer to supercritical carbon dioxide flowing upward vertical tube with highly conducting surroundings

机译:实验性传热至超临界二氧化碳,在高传导环境中向上流动至垂直管

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摘要

This paper presents heat transfer characteristics of supercritical carbon dioxide flow inside vertical circular pipe surrounded by highly conducting material, and develops an adequate tool to test the performance of available heat transfer correlations with. The possible situations are illustrated for the nuclear power plant to which the above-mentioned geometric configuration might be applicable. An experimental loop with vertical circular geometry is designed and constructed to test the upward flow in supercritical state when the axial heat transfer is enhanced by the surrounding metals, resulting in a wall boundary condition between the constant heat flux and temperature. The set of correlations and important findings are critically reviewed from extensive literature survey. Incorporating nondimensional groups resorting to past insights from the available literature, a convective heat transfer correlation is proposed. The optimization procedure is described which utilizes a random walk method along with the in-house finite element heat transfer code to determine the coefficients of the proposed heat transfer correlation. The proposed methodology can be applied to evaluation of heat transfer when the heat transfer coefficient data cannot directly be determined from the experiment.
机译:本文介绍了由高导热材料包围的垂直圆形管道内超临界二氧化碳流动的传热特性,并开发了一种适当的工具来测试与之相关的可用传热性能。示出了可能适用于上述几何构造的核电站的可能情况。设计并构建了具有垂直圆形几何形状的实验回路,以在轴向传热被周围金属增强时在超临界状态下测试向上流动,从而在恒定热通量和温度之间产生壁边界条件。广泛的文献调查对这组相关性和重要发现进行了严格审查。结合无量纲的方法,利用现有文献中的以往见识,提出了对流换热相关性。描述了优化过程,该过程利用随机游动方法以及内部有限元热传递代码来确定所提出的热传递相关系数。当不能从实验中直接确定传热系数数据时,所提出的方法可用于评估传热。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2012年第9期|p.573-584|共12页
  • 作者

    Hyung M. Son; Kune Y. Suh;

  • 作者单位

    Department of Nuclear Engineering, Seoul National University, Rm.32-215,1 Gwanak Ro.Gwanak Gu,Seoul 151-744,Republic of Korea;

    Department of Nuclear Engineering, Seoul National University, Rm.32-215,1 Gwanak Ro.Gwanak Gu,Seoul 151-744,Republic of 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
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