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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。
Experimental research on the upper cavity breaking water loss accident was carried out on the simulation test rig HRTL-5 of 5 MW nuclear reactor, and the experimental results on the pressure attenuation and water loss were given. It can be seen that the pressure in the system, the breaking area, the quality of the water vapor in the system, the operating status of the second circuit and the heating power affect the speed of the pressure change in the system. For the breakwater loss process of two-phase separator system with saturated pressure, the hypothesis of quasi-steady state was used to establish the basic relation and the expression of pressure and water change in the system was derived. It provides a simple and effective analysis tool for the safety analysis of nuclear heating reactors and other similar systems.