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Experimental investigation of temperature and heat distribution across 220 MWe Indian PHWR channel under boil-off condition

机译:截止条件下220 MWE印度PHWR通道温度和热分布的实验研究

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摘要

Under very low probability postulated accident like LOCA with unavailability of ECCS, the moderator heat sink maintains the channel integrity by providing adequate cooling. As the cooling is external to channel, the circumferential as well axial temperature gradient exists within the channel internals. An experimental set-up was fabricated to simulate the boil-off condition during a postulated accident in NPP. The experiments were conducted at average fuel bundle temperature 600 degrees C, 800 degrees C and 1100 degrees C with superheated mixture of steam and argon. The minimum and maximum temperature in CT, PT and fuel bundle were diametrically opposite to each other; the circumferential as well axial temperature gradient increased with an increase in bundle temperature. The rate of moderator heat absorption increases with increase in bundle temperature. The moderator was successfully able to prevent a breach in the channel; it proved to be the ultimate heat sink during a postulated LOCA with unavailability of ECCS. (C) 2020 Elsevier Ltd. All rights reserved.
机译:在非常低的概率假设事故,如LOCA,具有ECC的不可用,主持人散热器通过提供足够的冷却来保持通道完整性。由于冷却是通道外部的,因此在通道内部内存在轴向温度梯度的周向。制造了一种实验设置,以在NPP的假发事故中模拟蒸发状况。通过过热的蒸汽和氩气,在平均燃料束温度600℃,800℃和1100℃下进行实验。 CT,Pt和燃料束中的最小温度彼此径向相反;随着束温度梯度的圆周随着束温度的增加而增加。温度吸热的速率随着束温度的增加而增加。主持人成功地防止了通道中的违规行为;被证明是在假设基因座期间的终极散热器,具有不可用的ECC。 (c)2020 elestvier有限公司保留所有权利。

著录项

  • 来源
    《Annals of nuclear energy》 |2020年第9期|107600.1-107600.10|共10页
  • 作者单位

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

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

    Bhabha Atom Res Ctr Reactor Safety Div Mumbai Maharashtra India;

    Bhabha Atom Res Ctr Reactor Safety Div Mumbai Maharashtra India;

  • 收录信息
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    ECCS; LOCA; PHWR; CT; PT; NPP;

    机译:ECC;道路;PHWR;CT;PT;NPP;

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