CAP1400非能动安全壳冷却系统(Passive Containment Cooling System,PCS)仍采用与AP600和AP1000相同的先进非能动设计理念。本研究针对CAP1400的非能动安全壳冷却系统,设计并建造了非能动安全壳冷却系统综合性能试验平台(Containment sa...CAP1400非能动安全壳冷却系统(Passive Containment Cooling System,PCS)仍采用与AP600和AP1000相同的先进非能动设计理念。本研究针对CAP1400的非能动安全壳冷却系统,设计并建造了非能动安全壳冷却系统综合性能试验平台(Containment safety vErification via integRal Test facility,CERT),开展了试验研究。对CAP1400非能动安全壳冷却系统综合性能试验验证需求,试验装置的设计特点、研究内容及代表性的试验结果进行了介绍。通过PCS综合性能试验的开展,研究了非能动安全壳冷却系统的事故响应特性及关键物理现象,为CAP1400的安全评审及相关安全分析程序验证提供了试验结果支撑。展开更多
The AP1000 with high safety is a generation III pressurized water reactor(PWR),its significant feature is passive safety system.However,its passive cooling can only maintain for 72 h and requires additional support fr...The AP1000 with high safety is a generation III pressurized water reactor(PWR),its significant feature is passive safety system.However,its passive cooling can only maintain for 72 h and requires additional support from inside or outside the plant.To solve this problem,this study utilized the WGOTHIC software to calculate and analyze the water inventory in the passive containment cooling water tank under different conditions.The results show that when the cooling water inventory is 6553.78 m3,the AP1000 nuclear power plants can achieve long-term,completely passive cooling without any inside or outside the plant.The same outcomes occur when 65-mm-thick containment wall increases the design pressure rating to 0.6 MPa at the cooling water inventory of 5673 m3.Also,the AP1000 shield building was accordingly improved.An ANSYS analysis of the structural stability of the shield building with a 6000 m3 cooling water inventory confirmed that the new design can meet the requirements of the seismic design and the safe residual heat removal requirements of a large-scale PWR.展开更多
文摘CAP1400非能动安全壳冷却系统(Passive Containment Cooling System,PCS)仍采用与AP600和AP1000相同的先进非能动设计理念。本研究针对CAP1400的非能动安全壳冷却系统,设计并建造了非能动安全壳冷却系统综合性能试验平台(Containment safety vErification via integRal Test facility,CERT),开展了试验研究。对CAP1400非能动安全壳冷却系统综合性能试验验证需求,试验装置的设计特点、研究内容及代表性的试验结果进行了介绍。通过PCS综合性能试验的开展,研究了非能动安全壳冷却系统的事故响应特性及关键物理现象,为CAP1400的安全评审及相关安全分析程序验证提供了试验结果支撑。
文摘The AP1000 with high safety is a generation III pressurized water reactor(PWR),its significant feature is passive safety system.However,its passive cooling can only maintain for 72 h and requires additional support from inside or outside the plant.To solve this problem,this study utilized the WGOTHIC software to calculate and analyze the water inventory in the passive containment cooling water tank under different conditions.The results show that when the cooling water inventory is 6553.78 m3,the AP1000 nuclear power plants can achieve long-term,completely passive cooling without any inside or outside the plant.The same outcomes occur when 65-mm-thick containment wall increases the design pressure rating to 0.6 MPa at the cooling water inventory of 5673 m3.Also,the AP1000 shield building was accordingly improved.An ANSYS analysis of the structural stability of the shield building with a 6000 m3 cooling water inventory confirmed that the new design can meet the requirements of the seismic design and the safe residual heat removal requirements of a large-scale PWR.
