国内三代核电机组严重事故管理的设想

Assumption of Severe Accident Management for Chinese Third Generation Nuclear Power Units

福岛核电事故后,与M310二代加改进型核电机组相比,国内三代核电机组在设计中较多采用了能动和非能动相结合的事故缓解系统,并采用了多项设计优化和改进,其堆芯损伤频率(CDF)和大规模释放频率(LRF)比M310二代加改进型机组大幅降低。在严重事故应对方面,国内三代机组的事故缓解能力比M310二代加改进型机组更强。国内三代机组的严重事故管理导则(SAMG)可以借鉴M310二代加改进型机组所采用的西屋业主联合会(WOG)SAMG体系,并在SAMG体系的结构上进行优化改进,这样无论是在硬件上还是软件上,使国内三代机组在严重事故管理方面都获得显著的提升。

After the accident in Fukushima nuclear power plant,it is more often to adopt a combination of active and passive accident mitigation systems in Chinese 3 rd generation nuclear power units,compared with the 2 nd generation plus nuclear power unit(M310).Chinese 3 rd generation nuclear power units adopt a number of optimization design and improvement are adopted.The core damage frequency(CDF)and large-scale radioactivity release frequency(LRF)of the Chinese 3 rd generation nuclear power unit is lower than that of the M310.What’s more,the accident mitigation capacity of Chinese 3 rd generation unit is greater in dealing with severe accidents.For the architecture of severe accident management guideline(SAMG)in the 3 rd generation units,we can learn from the WOG(Westinghouse Owner Group)’s SAMG systems,which are used in2 nd-plus improved units(M310).After SAMG’s structures have been optimized,the severe accident management of the 3 rd generation units will be improved greatly both in hardware and software.