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HT-7U纵场磁体CICC导体设计
引用本文:陈灼民,翁佩德,李保增,毕延芳. HT-7U纵场磁体CICC导体设计[J]. 低温物理学报, 2003, 25(4): 313-318
作者姓名:陈灼民  翁佩德  李保增  毕延芳
作者单位:中国科学院等离子体物理研究所,合肥,230031
摘    要:国家“九、五”重大科学工程HT-7U托卡马克(Tokamak)是一个全超导核聚变实验装置,装置主机包含有16个纵场(TF)超导线圈和14个极向场(PF)超导线圈.线圈采用NbTi CICC导体(Cable in-Conduit Conductor)绕制,用超临界氦迫流冷却.本介绍CICC导体的设计和导体短样的测试结果.

关 键 词:HT-7U托卡马克装置 导体设计 核聚变装置 纵场磁体 CICC导体 超导线圈 管装超导电缆
修稿时间:2003-03-15

CICC CONDUCTOR DESIGN FOR HT-7U TF MAGNETS
CHEN ZHUO MINWENG PEI DELI BAO ZENGBI YAN FANG Institute of Plasma Physics,Chinese Academy of Sciences,Hefei. CICC CONDUCTOR DESIGN FOR HT-7U TF MAGNETS[J]. Chinese Journal of Low Temperature Physics, 2003, 25(4): 313-318
Authors:CHEN ZHUO MINWENG PEI DELI BAO ZENGBI YAN FANG Institute of Plasma Physics  Chinese Academy of Sciences  Hefei
Affiliation:CHEN ZHUO MINWENG PEI DELI BAO ZENGBI YAN FANG Institute of Plasma Physics,Chinese Academy of Sciences,Hefei230031
Abstract:HT 7U Tokamak is a overall superconducting device. It consists of 16 TF and 14 PF superconducting coils. It will be wound using CICC conductors, cooled with supercritical helium. This paper describes the design of TF conductors and properties testing of the all size samples.
Keywords:CICC   Conductor design   Stability
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