Non-Heating Experimental Study on External Reactor Vessel Cooling
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摘要: 压力容器外部冷却(ERVC)作为一项重要的严重事故缓解策略,可以将事故进程终结在压力容器内,实现熔融物堆内滞留(IVR)。但在核电厂应用ERVC策略之前,需要对其流动和传热过程进行实验研究。本实验采用1∶1模拟循环高度的切片实验装置模拟中国改进型三环路压水堆(CPR1000)压力容器外部冷却两相自然循环过程,研究其外部冷却流道结构及尺寸对外部冷却流动的影响。实验结果表明:进出口面积、贯穿件及保温层结构等对外部流动存在着不同程度的影响,其中进出口面积对循环流量的影响是主要的,但贯穿件对传热现象的影响需要进一步的分析和验证。试验中注气流量与回路循环流量的最大测量误差分别为12.9%和3.4%。
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关键词:
- 压力容器 /
- 外部冷却 /
- 自然循环 /
- 两相流动 /
- 中国改进型三环路压水堆
Abstract: As a key severe accident management strategy,External Reactor Vessel Cooling （ERVC） could terminate the physical process in the reactor pressure vessel and achieve the in-vessel molten debris retention. However,the strategy still needs to be investigated before its application in nuclear power plants. A slice geometry,full scale simulation experiment facility is designed to observe and investigate the two phase natural circulation of ERVC in CPR1000. The study is focused on the effects of the flow path geometry and size on the natural circulation. The experiment results reveal that the inlet/outlet area,penetration tubes and insulation influence the flow process at different levels and the inlet/outlet areas shows a dominating effect on the mass flow rate. The effect of penetration tubes on the boiling heat transfer need to be further evaluated. The maximum measured errors of air injection flowrate and circulation flowrate are 12.9% and 3.4% respectively.-
Key words:
- Pressure vessel /
- External cooling /
- Natural circulation /
- Two phase flow /
- CPR1000
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