摘要
基于聚变实验装置近期可达到的堆芯ＤＴ等离子体参数水平，在一维燃耗计算和优化分析的基础上，验证了氚自持、年约处理２９ 个同等热功率压水堆年产的长寿命锕系元素和一定数量裂变产物的次临界聚变嬗变堆带有双冷却系统高性能包层的中子学可行性，并给出了初步的设计方案。
A preliminary conceptual design of high performance dual cooled blanket in a spherical tokamak fusion driven transmuter has been proposed based on the core D T plasma parameter level achieved or to be achieved in the near future. The calculation shows that this kind of blanket is fritium self sustainable and could safely transmute the long lived actinides produced by 102 GWe·year PWRs, with several tons of fission products per year and 11600 MW thermal power output.
出处
《核科学与工程》
CSCD
北大核心
1999年第3期215-220,共6页
Nuclear Science and Engineering
