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为研究一体化布置的核供热堆在发生破口失水事故中破口大小和从中间回路排出热量减少对断流过程的影响，选用不同的破口尺寸和不同的二回路工作状态，在５ＭＷ核供热堆热工水力模拟回路ＨＲＴＬ－５上进行了实验研究。稳态运行工况的系统压力为１．５ＭＰａ，在发生小破口失水事故后，加热功率维持为额定功率的５％以模拟剩余发热情况。实验研究并比较了不同条件下压力、温度、循环流量、液位和失水量等重要参数的变化。这些实验数据为核供热堆的安全分析提供了实验依据。
In order to study the influence of the size of the integrated heating reactor on the breach in the event of breach of water loss and the reduction of heat output from the intermediate circuit on the interrupting process, different breaking sizes and different working states of the second circuit are adopted. 5MW nuclear heating reactor thermal hydraulic simulation circuit HRTL-5 on the experimental study. The system pressure for steady-state operating conditions was 1.5 MPa. After a small break-head water loss accident, the heating power was maintained at 5% of rated power to simulate the remaining heating conditions. Experimental study and comparison of pressure, temperature, circulating flow, liquid level and water loss and other important parameters under different conditions. These experimental data provide the experimental basis for the safety analysis of nuclear heating reactor.