| 上空腔破口失水时的压力衰减过程和失水量 |
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| 引用本文： | 博金海,张佑杰,姜胜耀.上空腔破口失水时的压力衰减过程和失水量[J].清华大学学报(自然科学版),1998(4). |
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| 作者姓名： | 博金海 张佑杰 姜胜耀 |
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| 作者单位： | 清华大学,核能技术设计研究院,北京,100084 |
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| 基金项目： | 国家“八五”科技攻关项目 |
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| 摘 要： | 在５ＭＷ核供热反应堆的模拟实验台架ＨＲＴＬ－５上进行了上空腔破口失水事故实验研究，给出了压力衰减和失水量的实验结果。可以看出系统压力、破口面积、系统内水汽质量、二回路运行状态和加热功率等因素对系统内压力变化速度的影响。对于具有一定压力处于饱和状态的汽水两相分离系统的破口失水过程，采用准稳态假设进行了分析，建立起基本关系式，导出了系统内压力和水量变化的表达式。对于核供热反应堆和其他类似系统的安全分析提供了一个简捷有效的分析工具。
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| 关 键 词： | 核供热反应堆 小破口失水事故 两相流 压力衰减 |
Pressure reducing and loss of water under SBLOCA at upper plenum of nuclear heating reactors |
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| BO Jinhai,ZHANG Youjie,JIANG Shengyao.Pressure reducing and loss of water under SBLOCA at upper plenum of nuclear heating reactors[J].Journal of Tsinghua University(Science and Technology),1998(4). |
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| Authors: | BO Jinhai ZHANG Youjie JIANG Shengyao |
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| Institution: | BO Jinhai,ZHANG Youjie,JIANG Shengyao Institute of Nuclear Energy Technology,Tsinghua University,Beijing 100084,China |
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| Abstract: | Experimental results of pressure reducing and loss of water under small break loss of coolant accident (SBLOCA) at upper plenum are presented. The experiments are carried out on the thermohydraulic test loop HRTL 5 of the 5MW nuclear heating reactor. The fundamental relations of saturated blowdown at upper plenum are presented. The expressions of variations for pressure and mass of water are deduced. It is seen from experimental results and expressions that important influence factors are system pressure, mass of water, system cooling capacity, area of break and heating power. These expressions are simple and clear for safety analysis of a nuclear heating reactor and similar systems. |
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