首页 | 本学科首页   官方微博 | 高级检索  
     

福岛事故后大型先进压水堆安全发展探讨
引用本文:叶成,郑明光,王明路,邱忠明,王勇.福岛事故后大型先进压水堆安全发展探讨[J].核安全,2014(1):50-54,70.
作者姓名:叶成  郑明光  王明路  邱忠明  王勇
作者单位:[1]上海交通大学,上海200240 [2]上海核工程研究设计院,上海200233 [3]浙江大学,杭州310058
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。

关 键 词:长期非能动  福岛事故  厂外救援

Safety Development Study of Advanced PWR Post Fukushima Accident
YE Cheng,ZHENG Mingguang,WANG Minglu,QIU Zhongming,Wang Yong.Safety Development Study of Advanced PWR Post Fukushima Accident[J].Nuclear Safety,2014(1):50-54,70.
Authors:YE Cheng  ZHENG Mingguang  WANG Minglu  QIU Zhongming  Wang Yong
Affiliation:1. Shanghai Jiao Tong University, Shanghai 200240, China; 2. Shanghai Nuclear Engineering Research and Design Institute, Shanghai 200233, China; 3. Zhejiang University, Hangzhou 310058, China)
Abstract: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.
Keywords:long-term passive safety  Fukushima accident  offsite rescue
本文献已被 CNKI 维普 等数据库收录!
设为首页 | 免责声明 | 关于勤云 | 加入收藏

Copyright©北京勤云科技发展有限公司  京ICP备09084417号