Development of advanced fuel inertial fusion targets

被引:7
|
作者
Tahir, NA [1 ]
Hoffmann, DHH [1 ]
机构
[1] Univ Erlangen Nurnberg, Inst Phys, D-91058 Erlangen, Germany
关键词
D O I
10.1017/S0263034600011150
中图分类号
O59 [应用物理学];
学科分类号
摘要
This paper discusses the implications of using different fuels, including pure deuterium, deuterium-tritium, deuterium-helium(3), and proton-boron(11), on safety and environmental compatibility of the fusion reactor, as well as on the driver requirements. Due to present-day technology limitations, it seems likely that the first generation of the fusion reactors will be based on a deuterium-tritium cycle. Such a scheme, howe:ver, would pose serious problems, including neutron activation and tritium handling. We show that by developing low-level tritium inertial fusion targets, one may substantially reduce the daily use of tritium in the reactor that may ultimately lead to a reduction in the overall tritium inventory in the power plant. Such reduced tritium targets will still generate sufficient energy to run the power plant economically.
引用
收藏
页码:575 / 587
页数:13
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