摘要
为研究一体化布置的核供热堆在破口失水事故时主回路冷却剂的自然循环断流过程，在５ＭＷ核供热堆热工水力模拟回路ＨＲＴＬ－５上进行了实验研究。在发生小破口失水事故后维持加热功率为额定功率的５％或２０％。实验结果表明，在自然循环断流过程中主回路可能发生倒流和流量振荡，这是由于破口失水和降压闪蒸联合作用的结果，是由于两相流体密度发生变化引起的。
The main loops of 5MW nuclear heating reactor and 200MW nuclear heating reactor are integral natural circulation systems. In case of loss of coolant occident (LOCA), while the water level reaches the upper edge of the inlet of the heat exchanger, flow break occurs. It has influnce on cooling core and stability of the main loop. An experiment described in this paper is carried out on the thermohydraulic test system HRTL 5 of the nuclear heating reactor. The position of the break is selected on the lower part of the exchanger. The system pressure is 1.5 MPa, the heating power under the accident is kept 5% or 20% of steady state power. Results show the heated element temperature is not too high and could not be burnout. But the flow oscillation in the primary coolant circuit occurs when the flow breaks completely at the end, which is unfavorable. The whole process of flow oscillation is discribed and its mechanism is inquired.
出处
《清华大学学报（自然科学版）》
EI
CAS
CSCD
北大核心
1997年第5期22-24,共3页
Journal of Tsinghua University(Science and Technology)
基金
国家"八五"科技攻关项目
关键词
供热堆
失水事故
自然循环
断流
安全
nuclear heating reactor (NHR)
loss of coolant accident (LOCA)
natural circulation
flow break
safety
instability
