Experimental simulation of hydrogen recycling at plasma-facing metal-hydride for fusion reactors

被引:3
|
作者
Borisko, VN [1 ]
Borisko, SV
Chebotarev, VV
Garkusha, IY
Klochko, YV
Lototsky, NM
Maslov, VI
Sereda, IN
Tereshin, VI
Zinoviev, DV
机构
[1] Kharkov Natl Univ, Kharkov, Ukraine
[2] NSC Kharkov, Inst Phys & Technol, Kharkov, Ukraine
[3] NAS Ukraine, Inst Mech Engn Problems, Kharkov, Ukraine
关键词
D O I
10.1238/Physica.Topical.103a00093
中图分类号
O4 [物理学];
学科分类号
0702 ;
摘要
In this paper we consider the possibility of using a hydride-forming Zr-V alloy as a first-wall material for fusion devices. Theoretical and experimental studies of the Zr-V hydride irradiation with flows of high-energy plasma particles have been performed. It is shown that the use of these materials allows the reduction of erosion of the first wall and also a better control of the hydrogen isotope recycling.
引用
收藏
页码:93 / 96
页数:4
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