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首页> 外文期刊>Nuclear Engineering and Design >Effect of eccentricity of pressure tube on circumferential temperature distribution of PHWR fuel bundle under postulated accident condition
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Effect of eccentricity of pressure tube on circumferential temperature distribution of PHWR fuel bundle under postulated accident condition

机译:假定事故条件下压力管偏心度对PHWR燃料束周向温度分布的影响

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摘要

For a large break Loss of Coolant Accident (LOCA) scenario with simultaneous failure of Emergence Core Cooling System (ECCS), the heat removal capability of coolant decreases, resulting in the complete voiding of the core of the reactor channel. In this scenario, radiation becomes dominating mode of heat transfer over the convection heat transfer from fuel bundle to Pressure Tube (PT). Due to this, the deformation of PT takes place either in the form of ballooning or sagging depending on prevailing internal pressure. The present paper aims to capture the circumferential temperature profile over the fuel bundle, PT and Calandria Tube (CT) undergoing sagging deformation of PT under a postulated LOCA with Loss of ECCS scenario. An experimental facility was designed and fabricated to simulate the sagging deformation of PT by changing the eccentricity "e" of PT with respect to the CT. The experiments were conducted at three different positions of PT i.e. e=0, e=4mm and e=8.5mm at 1100 degrees C fuel bundle temperature. The experimental results showed that the eccentricity of PT strongly affected the circumferential temperature distribution over the fuel bundle, PT and CT. The variation of temperature along the circumference of fuel bundle and PT at e=0 was insignificant, however, for other positions, this variation in temperature was quite significant. The bottom nodes of fuel bundle showed a decrease in temperature with an increase in eccentricity. Similar observations are also made for PT. On the other hand, the temperature at the bottom nodes of the CT increased for higher eccentricity between PT and CT. The experiments predict the temperature behavior for all the channel components for a decay power of 2% full power which is expected during such scenario.
机译:对于大的破损冷却剂事故(LOCA)情景,同时出现紧急堆芯冷却系统(ECCS)故障,冷却剂的散热能力降低,导致反应堆通道的堆芯完全排空。在这种情况下,辐射成为从燃料束到压力管(PT)的对流传热的主要传热模式。因此,取决于主要的内部压力,PT的变形以膨胀或下垂的形式发生。本文的目的是在假定的LOCA和ECCS损失情景下,捕获经历PT下垂变形的燃料束,PT和Calandria管(CT)上的圆周温度曲线。设计并制造了一个实验设备,通过改变PT相对于CT的偏心率“ e”来模拟PT的下垂变形。实验在PT的三个不同位置进行,即e = 0,e = 4mm和e = 8.5mm,温度为1100摄氏度的燃料束温度。实验结果表明,PT的偏心度强烈影响燃料束,PT和CT上的圆周温度分布。在e = 0时,沿着燃料束和PT的圆周的温度变化不明显,但是,对于其他位置,这种温度变化非常显着。燃料束的底部节点显示温度随偏心率的增加而降低。对于PT也有类似的观察。另一方面,由于PT和CT之间的偏心率较高,因此CT底部节点的温度升高。实验预测了在这种情况下预期的2%全功率衰减功率下所有通道组件的温度行为。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2018年第5期|274-281|共8页
  • 作者单位

    Indian Inst Technol, Dept Mech & Ind Engn, Roorkee 247667, Uttar Pradesh, India;

    Indian Inst Technol, Dept Mech & Ind Engn, Roorkee 247667, Uttar Pradesh, India;

    Bhabha Atom Res Ctr, Bombay 400085, Maharashtra, India;

    Bhabha Atom Res Ctr, Bombay 400085, 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
  • 中图分类
  • 关键词

    LOCA; ECCS; Fuel bundle; PT; CT; Moderator;

    机译:LOCA;ECCS;燃料束;PT;CT;主持人;

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