| 核供热堆失水事故模拟实验研究 |
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| 引用本文： | 博金海,张佑杰,吴少融,张雪松,何学东.核供热堆失水事故模拟实验研究[J].清华大学学报(自然科学版),1995(6). |
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| 作者姓名： | 博金海 张佑杰 吴少融 张雪松 何学东 |
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| 作者单位： | 清华大学核能技术设计研究院 |
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| 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。
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| 关 键 词： | 失水事故 核供热堆 固有安全性 |
Experimental simulation on LOCA of a nuclear heating reactor |
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| Bo Jinhai, Zhang Youjie, Wu Shaorong, Zhang Xuesong, He Xuedong Institute of Nuclear Energy Technology,Tsinghua University.Experimental simulation on LOCA of a nuclear heating reactor[J].Journal of Tsinghua University(Science and Technology),1995(6). |
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| Authors: | Bo Jinhai Zhang Youjie Wu Shaorong Zhang Xuesong He Xuedong Institute of Nuclear Energy Technology Tsinghua University |
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| 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. |
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| Keywords: | LOCA(loss of coolant accident) nuclear heating reactors inherent safety |
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