• DocumentCode
    783323
  • Title

    Mechanical design and analysis of joints for the ITER PF coils

  • Author

    Libeyre, P. ; Decool, P.

  • Author_Institution
    CEA/CADARACHE, St. Paul-Lez-Durance, France
  • Volume
    12
  • Issue
    1
  • fYear
    2002
  • fDate
    3/1/2002 12:00:00 AM
  • Firstpage
    586
  • Lastpage
    590
  • Abstract
    The Poloidal Field (PF) coils of the International Thermonuclear Experimental Reactor (ITER) are designed with NbTi cable-in-conduit conductors (CICCs) wound in double pancakes which are connected in series by joints. These joints have to operate in the poloidal magnetic field which generate large varying forces. The conceptual design of the joints is based on the overlap concept with twin-boxes and includes a tie-bar to carry the tensile load and a clamping support to resist the radial and vertical loads. The mechanical analysis is performed with several finite-element models of the joint area. It is shown that the design allows to keep both the tensile stress in the conductor and the shear stress in the insulation within acceptable limits.
  • Keywords
    Tokamak devices; cable jointing; cables (electric); finite element analysis; fusion reactor design; mechanical strength; niobium compounds; shear strength; stress-strain relations; superconducting coils; ITER PF coils; International Thermonuclear Experimental Reactor; NbTi; cable-in-conduit conductors; clamping support; double pancakes; finite-element models; joints; mechanical design; poloidal field coils; poloidal magnetic field; shear stress; tensile load; tie-bar; twin-boxes; Clamps; Coils; Conductors; Inductors; Magnetic analysis; Magnetic fields; Niobium compounds; Tensile stress; Titanium compounds; Wounds;
  • fLanguage
    English
  • Journal_Title
    Applied Superconductivity, IEEE Transactions on
  • Publisher
    ieee
  • ISSN
    1051-8223
  • Type

    jour

  • DOI
    10.1109/TASC.2002.1018472
  • Filename
    1018472