CPR1000核电站严重事故重要缓解措施与严重事故序列

Severe Accident Mitigation Measure and Severe Accident Sequence of CPR1000 Nuclear Power Plant

CPR1000核电站采用非能动氢气复合器、稳压器卸压功能延伸以及安全壳卸压过滤排放系统作为严重事故的预防和缓解措施,保证在严重事故条件下核电站安全壳的完整性不受损坏,保护环境周围的居民不受核辐射的危害。通过相关严重事故谱分析,选取冷却剂管道热段双段断裂+失去应急堆芯冷却系统、全厂断电、主蒸汽管道断裂+失去喷淋、失水未能紧急停堆的预计瞬态(ATWS)这4种严重事故作为CPR1000核电站的重要严重事故序列,包络了所有安全壳内氢气产生速度快浓度高、安全壳超压、冷却剂系统发生高压熔堆、反应堆不能停堆等最严重的事故。

The passive autocatalytic recombiners,pressurizer depressurization function extension (prevention high pressure melt core) and containment pressure relief and filter releasing system are used as the prevention and mitigation measures of severe accidents to prevent and mitigate the consequences of severe accidents in CPR100 nuclear power plant,to ensure the integrity of the containment of CPR1000 nuclear power plant under severe accidents and thus to protect the surrounding residents from the dangers of nuclear radiation. Based on the spectrum analysis of severe incidents,the LBLOCA + loss of safety injection pumps,station blackout,loss of all feed water +anticipated transient without scram and MSLB + loss of containment spray are selected as the important severe accident sequence.