DocumentCode :
1947481
Title :
Overview of ITER magnet system and European contribution
Author :
Sborchia, C. ; Soto, E. Barbero ; Batista, R. ; Bellesia, B. ; Oliva, A. Bonito ; Rebollo, E. Boter ; Boutboul, T. ; Bratu, E. ; Caballero, J. ; Cornelis, Marc ; Fanthome, J. ; Harrison, R. ; Losasso, M. ; Portone, A. ; Rajainmaki, H. ; Readman, P. ; Vale
Author_Institution :
ITER Dept., Fusion for Energy, Barcelona, Spain
fYear :
2011
fDate :
26-30 June 2011
Firstpage :
1
Lastpage :
8
Abstract :
The superconducting magnet system of ITER consists of four main sub-systems: Toroidal Field (TF) coils, Central Solenoid (CS) coils; Poloidal Field (PF) coils; and Correction Coils (CC). Like many other ITER systems, the magnet components are supplied in-kind by six Domestic Agencies (DAs). The technical specifications, manufacturing processes and procedures required to fabricate these components are particularly challenging. The management structure and organization to realize this procurement within the tight ITER construction schedule is very complex. Fusion for Energy (F4E), the European Domestic Agency for ITER, is in charge of about 25% of the contribution to the ITER magnet system, namely part of the TF and PF conductors, 10 TF coils, 5 PF coils and 9 TF system pre-compression rings. Good progress towards full scale construction has been achieved with the launch of large manufacturing contracts for the production of the superconductor lengths, the fabrication of two full-scale prototypes of the TF coil radial plates, and the start-up of the contract for the construction of 10 TF winding packs. Several tons of advanced Nb3Sn and NbTi strand have been produced, large cabling and jacketing facilities for the conductors and winding lines for the TF coils are being set-up. Tendering actions for the PF coils and pre-compression rings are in progress. Later in 2011 the contracts for the production of the TF radial plates and insertion of the TF coils in the cases will also be launched. This paper reports the progress of the F4E activities as per June 2011.
Keywords :
Tokamak devices; fusion reactor design; fusion reactor materials; plasma toroidal confinement; superconducting coils; superconducting magnets; windings; European Domestic Agency; ITER magnet system; central solenoid coils; correction coils; jacketing facilities; large cabling facilities; manufacturing process; poloidal field coils; precompression rings; superconducting magnet system; toroidal field coil radial plates; toroidal field coils; winding lines; Cable shielding; Conductors; Copper; Europe; Qualifications; Superconducting cables; Welding; ITER; Nb3Sn strand; PF coils; TF coils; radial plates; superconducting coils;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Fusion Engineering (SOFE), 2011 IEEE/NPSS 24th Symposium on
Conference_Location :
Chicago, IL
ISSN :
1078-8891
Print_ISBN :
978-1-4577-0669-1
Electronic_ISBN :
1078-8891
Type :
conf
DOI :
10.1109/SOFE.2011.6052218
Filename :
6052218
Link To Document :
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