DocumentCode
3129616
Title
Progress on R&D and design work for the ITER toroidal field coils
Author
Sborchia, C. ; Fillunger, H. ; Maix, R. ; Salpietro, E.
Author_Institution
EFDA CSU, Garching, Germany
fYear
2003
fDate
14-17 Oct. 2003
Firstpage
432
Lastpage
435
Abstract
The European Participant Team of ITER has assessed and validated the design and manufacturing of the ITER toroidal field (TF) coils with the production and test of one model coil, the toroidal field model coil (TFMC), and the fabrication of three full scale sections of the TF coil cases. A vast campaign of development and qualification of strands, cables, joints, insulation systems and structural materials has also been carried out. The R&D work has validated the choice of the superconducting strands and structural materials, as well as the manufacturing techniques and procedures for the winding, electrical joints and cases. The main goal of this paper is to highlight the impact of the European R&D results on the design of the ITER TF coil.
Keywords
Tokamak devices; plasma toroidal confinement; superconducting coils; European R&D results; ITER toroidal field coil design; ITER toroidal field coil manufacturing; R&D work; TF coil cases; cables; electrical joints; insulation systems; manufacturing techniques; structural materials; superconducting strands; toroidal field model coil; winding; Fabrication; Joining materials; Production; Qualifications; Research and development; Superconducting cables; Superconducting coils; Superconducting materials; Testing; Virtual manufacturing;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on
Print_ISBN
0-7803-7908-X
Type
conf
DOI
10.1109/FUSION.2003.1426676
Filename
1426676
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