【摘要】 叙述了位于核供热堆堆芯上方注硼管位置的中小尺寸管道破裂引起的小破口失水事故实验研究。在核供热堆热工水力学模拟实验回路ＨＲＴＬ－５上，对停堆后堆内有剩余功率的小破口失水事故进行了模拟实验，给出了小破口失水事故发生后，系统压力、温度、堆芯元件壁温、堆内冷却剂排放量、液位、空泡份额等重要参数的变化曲线，以及对低温堆安全性的影响。更多还原

【Abstract】 An experiment of a small break of boron injection pipe above reactor core is described in this paper. The experiment was carried out on the thermohydraulic test system HRTL-5 for the nuclear heating reactor. The system pressure, temperature, the wall temperature of core, the liquid level, the void fraction and the discharged coolant mass etc in the test were studied under the conditions that there is residual power after the reactor shutdown. The effect on nuclear heating reactor safety is given in this paper.更多还原