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
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