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

页码：1750 / 1759

页数：10

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