Title :
Development of Fine Filament NbTi Superconducting Strands for ITER
Author :
Liu, W.T. ; Liu, X.H. ; Feng, Y. ; Xie, H.J. ; Wang, T.C. ; Li, J.F.
Author_Institution :
R&D Div., Economic & Technol. Dev. Zone, Western Supercond. Technol. Co., Ltd., Xi´´an, China
fDate :
6/1/2010 12:00:00 AM
Abstract :
The NbTi superconducting wires are used for the Poloidal Field (PF) coil of International Thermonuclear Experimental Reactor (ITER). Western Superconducting Technologies Co., Ltd. (WST) has produced conventional NbTi superconducting strand by single stacking for ITER. The final strands has been heat-treated with different duration. The properties of the NbTi strands meet the requirements to ITER PF strand specification. The diameter of the strand is 0.73 mm and filament diameter is 7.8 . The multifilament composite strand is made up of Nb-Ti filaments embedded in a high purity Cu matrix. This paper presents the results of comparative investigations on critical currents(Ic), critical current density(Jc), AC losses of the strands.
Keywords :
Tokamak devices; critical current density (superconductivity); heat treatment; magnetic hysteresis; materials preparation; niobium alloys; superconducting coils; superconducting magnets; titanium alloys; type II superconductors; wires (electric); ITER NbTi superconducting strands; International Thermonuclear Experimental Reactor; NbTi; NbTi superconducting strand development; NbTi superconducting wires; Western Superconducting Technologies; conventional NbTi superconducting strand; fine filament NbTi superconducting strands; heat treatment; high purity copper matrix; multifilament composite strand; poloidal field coil; size 0.73 mm; size 7.8 mm; strand AC losses; strand critical current density; AC losses; ITER; NbTi superconducting strands; critical currents;
Journal_Title :
Applied Superconductivity, IEEE Transactions on
DOI :
10.1109/TASC.2009.2039474
