• DocumentCode
    3130433
  • Title

    Structural response of the DIII-D toroidal field coil to increased lateral loads

  • Author

    Reis, E.E. ; Chin, E.

  • Author_Institution
    Gen. Atomics, San Diego, CA, USA
  • fYear
    2003
  • fDate
    14-17 Oct. 2003
  • Firstpage
    577
  • Lastpage
    580
  • Abstract
    Recent calibration shots in which full toroidal field (TF) coil current interacted with the maximum poloidal field coils have produced increased lateral loads on the outer sections of the TF-coil. The increased lateral loads have resulted in deflections that have been sufficient to cause the TF-coil to contact adjacent equipment and produce a transient short to ground within the coil. The six outer turns of each TF-coil bundle are clamped together by insulated preloaded studs to provide increased bending stiffness. These sections of the outer bundles depend on friction to react the lateral loads as a bundle rather than six individual turns. A major concern is that the increased loads will produce slip between turns resulting in excessive lateral deflections and possible damage to the insulating sleeve on the preloaded studs. A finite element structural model of the TF-coil was developed for the calculation of deflections and the shear load distribution throughout the coil for the applied lateral loads from a full current calibration shot. The purpose of the updated structural model is to correlate the applied lateral loads to the total shear force between the unbonded sections of the outer turns. An allowable integrated lateral load applied to the outer turns is established based on the maximum shear force that can be reacted by friction. A program that calculates the magnetic fields and integrated lateral load along the outer turns can be incorporated into the plasma control system. The integrated load can then be compared to the calculated allowable value prior to execution of calibration shots. Calibration shots with a calculated total lateral load greater than the allowable value will be prevented.
  • Keywords
    Tokamak devices; coils; electromagnets; finite element analysis; physical instrumentation control; plasma toroidal confinement; plasma transport processes; DIII-D toroidal field coil; bending stiffness; calibration shots; coil bundle; finite element structural model; friction; full toroidal field coil current; lateral load deflections; magnetic fields; maximum poloidal field coils; plasma control system; preloaded studs; shear force; shear load distribution; structural response; Bonding; Calibration; Clamps; Coils; Contacts; Finite element methods; Friction; Insulation; Plasmas; Toroidal magnetic fields;
  • 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.2003.1426713
  • Filename
    1426713