R&D Towards HTS Current Leads for ITER

The ITER Organization (IO) and the Institute of Plasma Physics at the Chinese Academy of Sciences (ASIPP) are jointly developing the 68 kA current leads using High Temperature Superconductors for the superconducting Toroidal Field (TF) magnet system of the International Thermonuclear Experimental Re...

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Bibliographic Details
Published in:IEEE transactions on applied superconductivity 2009-06, Vol.19 (3), p.1500-1503
Main Authors: Bauer, P., Yanfang Bi, Anyi Cheng, Devred, A., Kaisong Ding, Xiongyi Huang, Kun Lu, Mitchell, N., Sahu, A.K., Guang Shen, Yuntao Song, Tingzhi Zhou
Format: Article
Language:English
Subjects:
Applied sciences
Bi2223
Design engineering
Electric connection. Cables. Wiring
Electrical engineering. Electrical power engineering
Electrical machines
Electromagnets
ELECTRONIC PRODUCTS
Electronics
Exact sciences and technology
fusion tokamak
HEAT EXCHANGERS
Helium cooled
High temperature superconductors
HTS current leads
Inductors
Miscellaneous
Nuclear and plasma sciences
Physics
Plasma temperature
Prototypes
Reactors
Semiconductor electronics. Microelectronics. Optoelectronics. Solid state devices
Superconducting devices
Superconducting films
Superconducting magnets
Superconducting tapes
SUPERCONDUCTIVITY
SUPERCONDUCTORS
TAPE
Tokamak devices
Toroidal magnetic fields
Various equipment and components
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Summary:The ITER Organization (IO) and the Institute of Plasma Physics at the Chinese Academy of Sciences (ASIPP) are jointly developing the 68 kA current leads using High Temperature Superconductors for the superconducting Toroidal Field (TF) magnet system of the International Thermonuclear Experimental Reactor, ITER. The proposed design consists of a conventional helium cooled heat exchanger operating between 65 K and 320 K and an HTS module covering the low temperature end using Bi-2223 tapes. The first HTS current lead prototypes will be tested in the EAST tokamak facility at ASIPP. This paper discusses the design of the first, 68 kA, TF HTS lead, which is the main emphasis of this first stage of the ITER current lead development program.
ISSN:1051-8223
1558-2515
DOI:10.1109/TASC.2009.2017838