反应堆冷却剂泵水力特性对大破口失水事故的影响研究

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Analysis of Effect of Hydraulic Characteristic of Reactor Coolant Pump on Large-Break Loss-of-Coolant Accident

National Key Laboratory of Reactor System Design Technology, Nuclear Power Institute of China, Chengdu, 610041, China

摘要: 以AP1000为研究对象,应用WCOBRA/TRAC程序对大破口失水事故进行模拟。主要分析4种不同的主泵特性曲线对系统压力、破口流量及包壳峰值温度的影响。研究结果表明,大破口失水事故下,由于主泵特性曲线的差异,导致喷放阶段及再淹没阶段的峰值包壳温度相差近150℃。通过合理优化或改进主泵特性可以为核电厂大破口失水事故带来更大的安全裕量。
- 主泵特性曲线 /
- 大破口失水事故 /
- AP1000
Abstract: The best estimate code WCOBRA/TRAC was utilized to model AP1000 Large-Break Loss-of-Coolant Accident.The effect of four different types of pump characteristics curves on the system pressure,break mass flow rate and peak clad temperature was analyzed.It was found that for LB LOCA accident,the difference on the peak clad temperature during the blow-down and the reflooding phase could be up to 150℃ with different pump curves.The safety margin of AP1000 could be improved through optimizing or improving the pump characteristics.
- Pump characteristics curve /
- Large-break loss-of-coolant accident /
- AP1000