• 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