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Experimental determination of thermal contact conductance between pressure and calandria tubes of Indian pressurised heavy water reactors

机译:印度加压重水反应堆压力管和排管的热接触传导的实验测定。

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摘要

Thermal contact conductance (TCC) is one of the most important parameters in determining the temperature distribution in contacting structures. Thermal contact conductance between the contacting structures depends on the mechanical properties of underlying materials, thermo-physical properties of the interstitial fluid and surface condition of the structures coming in contact. During a postulated accident scenario of loss of coolant with coincident loss of emergency core cooling system in a tube type heavy water nuclear reactor, the pressure tube is expected to sag/balloon and come in contact with outer cooler calandria tube to dissipate away the heat generated to the moderator. The amount of heat thus transferred is a function of thermal contact conductance and the nature of contact between the two tubes. An experimental facility was designed, fabricated and commissioned to measure thermal contact conductance between pressure tube and calandria tube specimens. Experiments were conducted on disc shaped specimens under axial contact pressure in between mandrels. Experimental results of TCC and a linear correlation as a function of contact pressure have been reported in this paper. (C) 2014 Elsevier B.V. All rights reserved.
机译:热接触电导(TCC)是确定接触结构中温度分布的最重要参数之一。接触结构之间的热接触电导率取决于下层材料的机械性能,组织液的热物理性能以及接触结构的表面状况。在假定的管型重水核反应​​堆冷却液损失与紧急堆芯冷却系统同时损失的事故情况下,压力管预计会下垂/膨胀并与外部冷却器排管接触以消散产生的热量给主持人。这样传递的热量是热接触电导率和两根管子之间接触性质的函数。设计,制造和调试了一个实验设备,以测量压力管和排管样品之间的热接触传导。在心轴之间的轴向接触压力下对圆盘状样品进行了实验。本文已经报道了TCC的实验结果和线性相关性作为接触压力的函数。 (C)2014 Elsevier B.V.保留所有权利。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2015年第4期|60-66|共7页
  • 作者单位

    Bhabha Atom Res Ctr, Reactor Design & Dev Grp, Bombay 400085, Maharashtra, India;

    Indian Inst Technol, Dept Mech Engn, Bombay 400076, Maharashtra, India;

    Indian Inst Technol, Dept Mech Engn, Bombay 400076, Maharashtra, India;

    Bhabha Atom Res Ctr, Reactor Design & Dev Grp, Bombay 400085, Maharashtra, India;

    OYC, Dept Atom Energy, Bombay, Maharashtra, India;

  • 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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