Interaction of CLAM Steel with Plasma in HT-7 Tokamak During High Parameter Operation  

作　　者：李春京 黄群英 冯岩 李建刚 孔明光 

机构地区：[1]Institute of Plasma Physics,Chinese Academy of Sciences,Hefei 230031,China [2]Institute of Solid State Physics,Chinese Academy of Sciences,Hefei 230031,China

出　　处：《Plasma Science and Technology》2007年第4期484-487,共4页等离子体科学和技术（英文版）

基　　金：supported by the National Natural Science Foundation of China (No.10375067);the Knowledge Innovation Program of Chinese Academy of Sciences

摘　　要：A Plasma Surface Interaction （PSI） experiment on China Low Activation Martensitic （CLAM） steel was done to check if CLAM steel could be used as a Plasma Facing Material （PFM）. A specimen with a diameter of 45 mm was exposed to 897 shots of deuterium plasmas with a total duration of 712 sec at a minor radius of 30 cm in HT-7 tokamak. During the exposure experiment, no observable influence was found on plasma performance. After exposure, the surface of the specimen seemed as smooth as before but with some colour change at the margin of the specimen. Even though some micro-damage, such as dense blisters, melting, splashing, depositions, and dust, was found on local surfaces with Scanning Electron Microscopic （SEM） observation. The reflectivity of the specimen decreased only slightly. All of these shows CLAM steel has good stability and irradiation resistance. With further optimization, it could possibly be used as the first mirror material for plasma diagnostics in tokamaks.A Plasma Surface Interaction （PSI） experiment on China Low Activation Martensitic （CLAM） steel was done to check if CLAM steel could be used as a Plasma Facing Material （PFM）. A specimen with a diameter of 45 mm was exposed to 897 shots of deuterium plasmas with a total duration of 712 sec at a minor radius of 30 cm in HT-7 tokamak. During the exposure experiment, no observable influence was found on plasma performance. After exposure, the surface of the specimen seemed as smooth as before but with some colour change at the margin of the specimen. Even though some micro-damage, such as dense blisters, melting, splashing, depositions, and dust, was found on local surfaces with Scanning Electron Microscopic （SEM） observation. The reflectivity of the specimen decreased only slightly. All of these shows CLAM steel has good stability and irradiation resistance. With further optimization, it could possibly be used as the first mirror material for plasma diagnostics in tokamaks.

关 键 词：CLAM PSI PFM 

分 类 号：TL631.24[核科学技术—核技术及应用]