钨在等离子体破裂时的表面损伤  

Surface damage of tungsten during plasma disruption

作　　者：李强[1] 何晓雄[1] 黄群英[2] 吴宜灿[2] 

机构地区：[1]合肥工业大学理学院,安徽合肥230009 [2]中国科学院等离子体物理研究所,安徽合肥230031

出　　处：《合肥工业大学学报（自然科学版）》2004年第10期1181-1183,共3页Journal of Hefei University of Technology：Natural Science

基　　金：国家自然科学基金资助项目(10375067)

摘　　要：在托卡马克类型的聚变装置中,面向等离子体材料在等离子体破裂过程中要承受剧烈的热负荷,这会使得面向等离子体材料表面受到严重的损伤。实验中将纯钨样品放入HT-7托卡马克的刮削层中,以研究等离子体与纯钨表面的作用。实验后发现样品表面产生了等离子体冲击痕和熔化斑痕。The surface of plasma facing materials in tokamak-type fusion reactors may be damaged severely due to the intense heat loads during plasma disruptions. In the paper,an experiment is made to investigate the surface damage of tungsten during a plasma disruption. In the experiment, samples of pure tungsten were placed in the scrape-off layer of HT-7 tokamak to study the interaction between plasma and the surface of samples. Analysis results by scanning electron microscopy show that plasma impacting traces and melting traces were found in the surface of samples.

关 键 词：HT-7托卡马克 等离子体 纯钨表面损伤 

分 类 号：O532.2[理学—等离子体物理]