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５ＭＷ核供热堆和２００ＭＷ核供热堆的主回路是一体化的自然循环系统．在破口失水事故中，当液位降至低于主换热器入口上沿以后会发生主回路冷却剂自然循环的断流过程，影响堆芯的冷却和系统的稳定性．当发生失水事故而且反应堆又不能完全停堆时这种影响更大．在５ＭＷ核供热堆热工水力模拟回路ＨＲＴＬ５上进行了实验．破口位置选在一回路换热器下部．模拟实验回路的加热段和上升段取几何相似，实验系统的流体与原型相同，并取相同的稳态运行工况．将实验系统调至稳态运行工况，系统压力调整到１．５ＭＰａ，在发生小破口失水事故后维持额定功率的２０％的加热功率．实验结果表明，在自然循环断流过程中，燃料元件不会出现超温以至于烧毁，但事故中发生的流量振荡对堆内构件的安全是不利的
The main circuit of 5MW nuclear heating reactor and 200MW nuclear heating reactor is an integrated natural circulation system. In the event of a loss of water breakage, when the liquid level drops below the upper edge of the inlet of the main heat exchanger, a flow-through process of the natural circulation of the main circuit coolant occurs, affecting the cooling of the core and the stability of the system. This effect is even greater when a water-cut accident occurs and the reactor can not be fully shutdown. In 5MW nuclear heating reactor thermal hydraulic simulation circuit HRTL 5 on the experiment. Select the location of the break in the lower part of a loop heat exchanger. The heating section and the ascending section of the simulation experiment circuit are similar in geometry. The fluid in the experimental system is the same as the prototype and takes the same steady-state operating conditions. The experimental system transferred to the steady-state operating conditions, the system pressure is adjusted to 1.5MPa, in the event of a small break after the accident, the loss of water to maintain the rated power of 20% of the heating power. The experimental results show that the fuel element will not over-temperature and burn out during the natural circulation and flow-off, but the flow oscillation occurred in the accident is unfavorable to the safety of the components in the reactor