TRITIUM IN THE FUEL-CYCLE OF A D-HE-3 FUSION-REACTOR

被引：2
|
作者：
NISHIKAWA, M
机构：
[1] Kyushu Univ, Fukuoka
来源：
FUSION TECHNOLOGY | 1992年 / 22卷 / 01期
关键词：
D-HE-3 FUSION REACTOR; TRITIUM; FUEL CYCLE;
D O I：
10.13182/FST92-A30063
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
Problems related to tritium in the fuel cycle of a D-He-3 fusion reactor are discussed. A bout 15 g/day of tritium is estimated to be exhausted from a 1-GW(electric) D-He-3 reactor. The cumulative amount of tritium in storage reaches approximately 80 kg after 30 yr of operation if all the tritium exhausted from the plasma is confined.
引用
收藏
页码：135 / 137
页数：3
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