CLAM钢、EUROFER97钢与钨在HT-7托卡马克中辐照后的表面分析  

Surface analysis of CLAM steel, EUROFER97 steel and W irradiated in HT-7 Tokamak

作　　者：李强[1] 黄群英[1] 郁金南 李建刚[1] 吴宜灿[1] 何晓雄 

机构地区：[1]中国科学院等离子体物理研究所 [2]中国原子能研究院,北京102413

出　　处：《核科学与工程》2004年第2期157-163,共7页Nuclear Science and Engineering

基　　金：国家自然科学基金资助项目(10375067);中国科学院知识创新工程资助项目

摘　　要：两种低活化马氏体钢(CLAM、EUROFER97)以及钨被放入HT-7托卡马克的刮削层中,以研究托卡马克装置中高温等离子体与低活化马氏体钢和钨表面的相互作用。通过SEM装置观察,发现某些样品的表面形貌发生了很大变化。低活化马氏体钢的表面起泡比较密集,钨的表面起泡比较稀少,且直径较大。在一些样品的表面,还观察到了等离子体灰尘以及明显的被等离子体冲击后的痕迹。另外,XPS分析发现样品表面的某些元素成分也发生了变化,而且处在托卡马克装置中不同位置处的样品,其表面硅的含量呈现出明显的规律性。Samples of two kinds of low activation ferritic/martensitic steels, i. e. CLAM steel and EUROFER97 steel, and W were irradiated in HT-7 Tokamak to investigate the interaction with plasma. Surface morphology observation of some samples with Scanning Electron Microscope (SEM) show great changes after irradiation. It is easy to observe the dense small bilisters on surfaces of CLAM steel, EUROFER97 steel and sparse big blisters the on surface of W when they are closer to the center plasma. Plas- ma dust and trace struck by plasma are observed on sample surfaces when they are farther to the center plasma. X-ray Photoelectron Spectroscopy (XPS) shows that chemical compositions of sample surfaces are changed, and it is obvious that the composition of silicon on sample surfaces due to its sputtering and redeposition varies with samples' distance from plasma.

关 键 词：HT-7托卡马克 表面分析 低活化马氏体钢 EUROFER97 钨 

分 类 号：TL631.24[核科学技术—核技术及应用]