Lithium carbide is prospective material for breeder of fusion reactor

被引：4
|
作者：
Alenina M.V. [1 ]
Kolotov V.P. [1 ]
Platov Y.M. [2 ]
机构：
[1] Vernadsky Institute of Geochemistry and Analytical Chemistry, Russian Academy of Sciences, Moscow
[2] Baikov Institute of Metallurgy and Materials Science, Russian Academy of Sciences, Moscow
来源：
Inorganic Materials: Applied Research | 2014年 / 5卷 / 2期
关键词：
Fusion reactor blanket; Lithium carbide; Tritium;
D O I：
10.1134/S2075113314020026
中图分类号：
学科分类号：
摘要：
It is shown that lithium carbide is a prospective material for breeder of fusion reactor. The lithium carbide equivalent dose rate reaches a biologically safe level (2.3×10-5 Sv/h) one minute after the irradiation with fusion reactor neutrons (with a fluence of 2×1023cm -2) is stopped. The yield of tritium from lithium carbide is 1.5-2.6 times higher than the corresponding yield from such lithium ceramics as Li4SiO4 and Li2TiO3. © 2014 Pleiades Publishing, Ltd.
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页码：149 / 153
页数：4
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