摘要
钠冷快堆是第四代核能系统国际论坛(GIF)公布的6种第四代先进反应堆中研发进展最快、最接近满足商业核电厂需要的堆型。钠冷快堆因其在固有安全性以及可增殖核燃料、嬗变长寿命放射性废物等方面的优势,得到了世界各国的重视。文章以中国第一座钠冷快堆——中国实验快堆(China Experimental Fast Reactor,CEFR)为例,介绍了钠冷快堆在设计及运行方面的安全特性。
The sodium-cooled fast reactor is the fastest prototype and the closest to com- mercialization for nuclear power plants amongst the six types of fourth generation reactors, as an- nounced at the Generation IV International Forum. Many countries are paying more and more at- tention to the research and development of these reactors, due to the inherent safety features, effi- cient utilization of uranium with the breeding of the plutonium, and transmutation of long-lived ac- tinides. The design and operational safety characteristics of the China Experimental Fast Reactor are reviewed in this paper.
出处
《物理》
CAS
北大核心
2016年第9期561-568,共8页
Physics
