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首页> 外文期刊>LA Houille Blanche >Two-phase flow parameters of a downcomer boiling during a postulated reflood phase of APR1400
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Two-phase flow parameters of a downcomer boiling during a postulated reflood phase of APR1400

机译:APR1400假定的回注阶段下水管沸腾的两相流参数

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摘要

Downcomer boiling phenomena is one of the key issues for a postulated large-break LOCA (LBLOCA) in a conventional pressurized water reactor, because it can degrade the hydraulic head of the coolant in the downcomer and consequently affect the reflood flow rate for a core cooling. To investigate the thermal hydraulic behavior in the downcomer region of the APR 1400, a test program for a downcomer boiling is being progressed for the reflood phase of a postulated LBLOCA. Test was performed in a one side heated rectangular test channel which was designed by adopting a full-pressure, full-height, and full-size downcomer-gap approach, but with the circumferential length was reduced 47.08-fold. The test consists of two steps : (Ⅰ) for the global two-phase flow parameters and (Ⅱ) fur the local two-phase flow parameters. The step-I test has already been completed. In the present paper, the experimental results of the step-Ⅱ test are introduced.
机译:降液管沸腾现象是常规压水反应堆中假定的大断裂LOCA(LBLOCA)的关键问题之一,因为它会降低降液管中冷却液的水压头,进而影响堆芯冷却的回油流量。为了研究APR 1400降液管区域的热力水力行为,正在为假定的LBLOCA的回油阶段开发降液管沸腾的测试程序。测试是在一侧加热的矩形测试通道中进行的,该通道通过采用全压,全高和全尺寸降液管间隙设计,但周长减少了47.08倍。该测试包括两个步骤:(Ⅰ)总体两相流参数和(Ⅱ)局部两相流参数。第一步测试已经完成。介绍了Ⅱ步试验的实验结果。

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  • 来源
    《LA Houille Blanche》 |2009年第4期|44-514-5|共10页
  • 作者单位

    Korea Atomic Energy Research Institute;

    Korea Atomic Energy Research Institute;

    Korea Atomic Energy Research Institute;

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  • 原文格式 PDF
  • 正文语种 eng
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