TRITIUM CONTENT OF A DT PELLET IN INERTIAL CONFINEMENT FUSION

被引:16
作者
KAWATA, S [1 ]
NAKASHIMA, H [1 ]
机构
[1] KYUSHU UNIV,DEPT ENERGY CONVERS ENGN,KASUGA,FUKUOKA 816,JAPAN
关键词
D O I
10.1017/S0263034600006728
中图分类号
O59 [应用物理学];
学科分类号
摘要
A numerical and analytical estimation and a one-dimensional hydrodynamic simulation show that a 30% reduction of the tritium content in a D-T pellet still gives sufficient energy output in a D-T inertial confinement fusion reactor. In other words, the tritium content can be reduced significantly without a significant reduction in the D-T fusion energy output. This new result also means that the tritium inventory can be reduced significantly before and during the reactor operation in the D-T inertial confinement fusion. This result comes from the contribution of a D-D reaction to the D-T reaction.
引用
收藏
页码:479 / 484
页数:6
相关论文
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