压水堆核电站全厂断电事故及辅助给水系统的缓解能力研究

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Study on SBO Accident and Mitigating Capability of Auxiliary Feedwater System for PWR

Department of Nuclear Science and Engineering, Naval University of Engineering, Wuhan, 430033, China

摘要: 以美国Surry核电站为参考对象,采用最佳估算程序SCDAP/RELAP5/MOD3.4,建立了一个典型的三环路压水堆核电站严重事故计算模型,对全厂断电(SBO)事故的物理现象及堆芯熔化进程进行了详细分析,并研究了全厂断电事故发生后辅助给水(AFW)分别持续1800s和3600s对事故的缓解效果。计算结果显示,辅助给水能有效地延缓堆芯熔化进程,大大推迟反应堆压力容器的失效时间,为操纵员恢复交流电源以及实施其它缓解措施赢得更多的时间。
- 严重事故 /
- 全厂断电 /
- 辅助给水 /
- 蠕变破裂失效
Abstract: Using the best estimate computer code SCDAP/RELAP5/MOD3.4 and Surry NPP as reference object,a representative three loops PWR severe accident calculation model is established and station blackout（SBO） induced core melt progression and phenomenon is analyzed.Effects are discussed when auxiliary fe-edwater（AFW） operates to mitigate the SBO accident progression 1800s and 3600s after SBO starting.Cal-culation results show that core melt progression and failure time of reactor pressure vessel is greatly delayed,thus the operator has more time available for AC recovery and other mitigation measures to prevent reactor pressure vessel failure.
- Severe accident /
- Station blackout /
- Auxiliary feedwater /
- Creep rupture failure