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福岛事故后大型先进压水堆安全发展探讨 被引量:6

Safety Development Study of Advanced PWR Post Fukushima Accident
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摘要 对福岛事故进行分析,指出在没有厂外救援的情况下,堆芯和乏燃料需要长期完全非能动冷却。通过在AP1000基础上的改进和对新型非能动系统的研究,说明了大型先进压水堆可以实现长期完全非能动冷却,从而实现无需厂外应急的第IV代核电厂安全目标,这也是大型先进压水堆安全发展的方向。 Fukushima accident was analyzed and the result shows the reactor core and the spent fuel pool need long-term passive cooling without offsite rescue.The improved designs based on the AP1000 and the studies of passive cooling system demonstrated that advanced PWRs can meet the requirement and achieve the goal of Generation IV nuclear power plants-offsite emergency is not required which is the future direction of advanced PWR.
出处 《核安全》 2014年第1期50-54,70,共6页 Nuclear Safety
关键词 长期非能动 福岛事故 厂外救援 long-term passive safety Fukushima accident offsite rescue
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参考文献15

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