OVERALL EVALUATION OF GRAPHITE AS PLASMA-FACING MATERIAL

被引：0
|
作者：
不详
机构：
来源：
JOURNAL OF THE ATOMIC ENERGY SOCIETY OF JAPAN | 1993年 / 35卷 / 12期
关键词：
GRAPHITE; THERMONUCLEAR REACTOR MATERIALS; EROSION; SUBLIMATION; CARBON BLOOM; RECYCLING; TRITIUM RETENTION; THERMAL SHOCK; DIVERTOR; HIGH HEAT FLUX COMPONENTS; BORON; BERYLLIUM; JT-60U; TRIAM-1M; LHD; ITER; REVIEWS;
D O I：
暂无
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
Described are the activities of Research Committee on Evaluation Study on Graphite as Plasma Facing Material. Atomic Energy Society of Japan, during the period from Oct. 1989 to Sep. 1993. The committee reviewed and discussed the present status of plasma facing components in present large fusion devices, characterizations for graphites, boron and beryllium, tritium inventory in plasma facing components, brazed components for high heat flux, neutron damage of graphite and divertor configuration of next devices.
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页码：1066 / 1075
页数：10
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