BERYLLIUM - A BETTER TOKAMAK PLASMA-FACING MATERIAL

被引：60
|
作者：
WILSON, KL [1 ]
CAUSEY, RA [1 ]
HSU, WL [1 ]
MILLS, BE [1 ]
SMITH, MF [1 ]
WHITLEY, JB [1 ]
机构：
[1] SANDIA NATL LABS,ALBUQUERQUE,NM 87185
来源：
JOURNAL OF VACUUM SCIENCE & TECHNOLOGY A-VACUUM SURFACES AND FILMS | 1990年 / 8卷 / 03期
关键词：
D O I：
10.1116/1.576843
中图分类号：
TB3 [工程材料学];
学科分类号：
0805 ; 080502 ;
摘要：
The plasma material interaction and high heat flux properties of beryllium are reviewed to determine its suitability as a plasma-facing component in magnetic fusion energy reactors. Consideration is given to beryllium's outgassing, erosion, and hydrogen retention characteristics. Its responses to normal and off-normal high heat fluxes are compared to graphite in both the as-received and the neutron-irradiated states. Beryllium's performance in present-day devices is assessed, and its expected behavior in future reactors is summarized. It is concluded that beryllium is potentially a better plasma-facing material than graphite and that more development and testing is warranted. © 1990, American Vacuum Society. All rights reserved.
引用
收藏
页码：1750 / 1759
页数：10
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