ITER 10kA高温超导电流引线试验件设计与测试  

Design and Test of 10kA HTSCL for ITER

作　　者：周挺志[1] 毕延芳[1] 丁开忠[1] 冯汉升[1] 黄雄一[1] 刘承连[1] 倪清[1] 沈光[1] 宋云涛[1] 

机构地区：[1]中国科学院等离子体物理研究所,安徽合肥230031

出　　处：《原子能科学技术》2013年第1期141-146,共6页Atomic Energy Science and Technology

基　　金：973计划资助项目(2008CB717900);ITER计划资助项目(2008GB102000)

摘　　要：本文介绍了10kA电流引线试验件的设计优化,主要描述了针对ITER所用与要求而设计的10kA电流引线的设计结构与加工,电子束焊接首次应用于电流引线的焊接工艺。说明了此电流引线试验件的测试性能;对目前的工艺与测试结果提出并讨论了可能的改进方案。The optimization of the design dimensions was introduced, and the design and manufacture of the ITER correction coil 10 kA high temperature superconductor (HTS) trial lead was mainly described. The electron beam welding (EBW) is firstly used in current lead manufacture. Some possible updating of the current leads was also discussed based on the test results.

关 键 词：聚变托卡马克 ITER 电流引线 高温超导 

分 类 号：TL631.2[核科学技术—核技术及应用]