摘要
合肥超导托卡马克ＨＴ－７Ｕ将是一个具有先进运行模式的核聚变实验装置，它的所有线圈将使用ＮｂＴｉ／ＣｕＣＩＣＣ（Ｃａｂｌｅ－ｉｎ－Ｃｏｎｄｕｉｔ－Ｃｏｎｄｕｃｔｏｒ）型超导体，并使用超临界氦迫流冷却。现在，用于中心螺管ＣＳ（ＣｅｎｔｒａｌＳｏｌｅｎｏｉｄ）模型线圈导体的制造已经完成，该导体长３７０米，外形尺寸是１７．４ｍｍ×１７．４ｍｍ，它含有１０８根Φ０．８５ＮｂＴｉ／Ｃｕ复合线和５４根Φ０．８５高纯铜线。
Hefei Tokamak HT-7U is a nuclear fusion experimental device with advanced operating modes. All of the coils will use NbTi/Cu Cable-in Conduit Conductor (CICC) cooled with forcedflow supercritical helium (SHe). Up to date, the conductor fabrication for the central solenoid (CS) model coil has been completed. The length of the CICC is 370m. The outer dimensions of the CICC are 17.4mm×17.4mm. The CICC consists of cabled 108 NbTi strands and 54 high pure copper (Cu) strands with the diameter of 0.85mm.
出处
《低温与超导》
CAS
CSCD
北大核心
1998年第3期9-13,共5页
Cryogenics and Superconductivity
