聚变堆装置中面向等离子体材料钨涂层的研究进展  

Research Development of Tungsten Coatings Used as Plasma Facing Materials for Fusion Reactor

作　　者：郭双全[1] 葛昌纯[1,2] 周张健[2] 刘维良[2,3] 

机构地区：[1]西南交通大学材料科学与工程学院,成都610031 [2]北京科技大学核材料研究所,北京100083 [3]景德镇陶瓷学院,景德镇333001

出　　处：《材料导报》2010年第3期93-97,共5页Materials Reports

基　　金：ITER973项目中国低活化钢(CLAM)若干关键科学问题研究(2008CB717802)

摘　　要：钨具有高的熔点、不与氚发生共沉积、与等离子体好的兼容性和低的腐蚀率等优点,是最有前景的一种面向等离子体材料。为了解决面向等离子体材料的制备及其与热沉材料连接问题,涂层技术在实验聚变堆装置中得到广泛应用。评述了目前实验聚变堆装置中面向等离子体材料钨涂层的研究进展。Tungsten, due to its high melting point, low tritium inventory, good compatibility with tusion plasma and low erosion rate under plasma loading, shows high promise as plasma facing materials. Coating technology has been widely applied to fusion reactor, which can fabricate the PFM and join it to heat sink materials simultaneously. In this paper, the current research progress on the tungsten coatings is reviewed.

关 键 词：聚变堆 面向等离子体材料 钨 涂层 

分 类 号：TL627[核科学技术—核技术及应用] V250[一般工业技术—材料科学与工程]