• 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