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徐銤, 杨红义. 钠冷快堆及其安全特性[J]. 物理, 2016, 45(9): 561-568. DOI: 10.7693/wl20160902
引用本文: 徐銤, 杨红义. 钠冷快堆及其安全特性[J]. 物理, 2016, 45(9): 561-568. DOI: 10.7693/wl20160902
XU Mi, YANG Hong-Yi. Safety properties of sodium-cooled fast reactors[J]. PHYSICS, 2016, 45(9): 561-568. DOI: 10.7693/wl20160902
Citation: XU Mi, YANG Hong-Yi. Safety properties of sodium-cooled fast reactors[J]. PHYSICS, 2016, 45(9): 561-568. DOI: 10.7693/wl20160902

钠冷快堆及其安全特性

Safety properties of sodium-cooled fast reactors

  • 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。

     

    Abstract: The sodium-cooled fast reactor is the fastest prototype and the closest to commercialization for nuclear power plants amongst the six types of fourth generation reactors, as announced at the Generation IV International Forum. Many countries are paying more and more attention to the research and development of these reactors, due to the inherent safety features, efficient utilization of uranium with the breeding of the plutonium, and transmutation of long-lived actinides.The design and operational safety characteristics of the China Experimental Fast Reactor are reviewed in this paper.

     

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