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核电站堆芯熔融物的处理措施
引用本文:冉刻,周涛,李精精.核电站堆芯熔融物的处理措施[J].水利电力机械,2011(10):77-81.
作者姓名:冉刻  周涛  李精精
作者单位:华北电力大学核热工安全与标准化研究所,北京102206
基金项目:国家自然科学基金资助(50976033); 华北电力大学校内“211”资助
摘    要:在分析核电站堆芯熔融物的结构特性、传热特点以及熔融物冷却处理策略的基础上,通过对AP1000,EPR,VVER-1000以及福岛核电站沸水堆4种堆芯熔融物处理措施的分析及比较中得出,压力容器内堆芯熔融物的冷却和包容对严重事故的缓解起着至关重要的作用。堆芯熔融物处理方式的不同,在一定程度上影响反应堆机组功率的适用范围,新一代堆型在堆芯熔融处理方式上较以前有明显改进;严重事故缓解措施的不同,反映了不同堆型设计理念的差异。深入研究了各种堆型熔融物的处理措施,对保障核电站安全具有重要价值。

关 键 词:核电站  堆芯熔融物  缓解措施  严重事故

Treatment measures of molten core of nuclear reactor
RAN Ke,ZHOU Tao,LI Jingjing.Treatment measures of molten core of nuclear reactor[J].Water Conservancy & Electric Power Machinery,2011(10):77-81.
Authors:RAN Ke  ZHOU Tao  LI Jingjing
Affiliation:(Institute of Nuclear Thermal-Hydraulic Safety and Standardization,North China Electric Power University,Beijing 102206,China)
Abstract:Based on the analysis of the structure features,the heat transfering characteristics of the nuclear reactor molten core and the cooling treatment strategy for the molten core,according to the analysis and comparison of the treanment measures for the molten cores of four type nuclear power plants,which are AP1000,EPR,VVER-1000 and the boiling-water reactor in Fukushima,Japan,it was confirmed that to cool and to contain the molten core in a pressure vessel have very important function for mitigating serious accidents.The difference in treatment mode of molten core influences the range of application of reactor unit power in a certain degree.The treatment mode of molten core of new reactor pattern is improved obviously comparing with the previous one.The difference in measures of different reactors for treatment serious accident reflect the difference in design concept of different reactor patterns.The remedial measures of molten core for various reactor patterns were researched in depth,which has important value for ensuring the safety of nuclear power plants.
Keywords:nuclear power plant  molten core  mitigating measure  serious accident
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