• DocumentCode
    1949362
  • Title

    Thermal-hydraulic simulation of 80 kA safety discharge in the ITER Toroidal Field Model Coil (TFMC) using the 4C code

  • Author

    Richard, L. Savoldi ; Bonifetto, R. ; Zanino, R. ; Heller, R.

  • Author_Institution
    Dipt. di Energetica, Politec. di Torino, Turino, Italy
  • fYear
    2011
  • fDate
    26-30 June 2011
  • Firstpage
    1
  • Lastpage
    5
  • Abstract
    The Toroidal Field Model Coil (TFMC) was extensively tested in 2001-2002, up to maximum transport current of 80 kA and peak field of ~ 10 T, in the TOSKA facility at the Karlsruhe Institute of Technology, Germany. Here we apply the 4C code, which was developed for the analysis of thermal-hydraulic transients in superconducting magnets, including winding, structures and cryogenic circuit, to the analysis of the TFMC safety discharge from 80 kA. The code is able to reproduce the main experimental features, within the limitations due to no more fully available information about the details of the cryogenic circuit, which play here a much more important role than at lower currents.
  • Keywords
    Tokamak devices; cryogenics; fusion reactor safety; plasma toroidal confinement; superconducting coils; superconducting magnets; ITER toroidal field model coil; TFMC safety discharge; TOSKA facility; cryogenic circuit; superconducting magnets; thermal-hydraulic simulation; winding; Accuracy; Approximation methods; Manifolds; Windings; Nuclear fusion; Simulation; Superconducting magnets; TFMC; Thermal-hydraulics;
  • 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.2011.6052297
  • Filename
    6052297