DocumentCode :
1221006
Title :
Design and Specifications of the ITER TF Coils
Author :
Sborchia, C. ; Fu, Y. ; Gallix, R. ; Jong, C. ; Knaster, J. ; Mitchell, N.
Volume :
18
Issue :
2
fYear :
2008
fDate :
6/1/2008 12:00:00 AM
Firstpage :
463
Lastpage :
466
Abstract :
The current design of the ITER Toroidal Field coils and structures, the main critical design and manufacturing issues, and the status of the procurement arrangements for these components, which will be released to the ITER parties in early 2008 to start the manufacturing contracts, are described. Some qualification and R&D work still required in preparation for the manufacture are also mentioned.
Keywords :
Tokamak devices; fusion reactor design; fusion reactor materials; heat treatment; plasma toroidal confinement; research and development; ITER magnet system; ITER toroidal field coil design; R&D; heat treatment; plasma confinement; structural component; Fusion; ITER; heat treatment; high voltage tests; impregnation; superconductor; toroidal field coils;
fLanguage :
English
Journal_Title :
Applied Superconductivity, IEEE Transactions on
Publisher :
ieee
ISSN :
1051-8223
Type :
jour
DOI :
10.1109/TASC.2008.921339
Filename :
4523021
Link To Document :
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