• DocumentCode
    2051307
  • Title

    Design and R&D for the central solenoid for the Compact Ignition Tokamak (CIT)

  • Author

    Thome, R.J. ; Pillsbury, R.D., Jr. ; Smith, B.A. ; Vieira, R. ; Thomas, P. ; Olmstead, M. ; Mann, W.R. ; Winn, P. ; Titus, P. ; Myatt, L.

  • Author_Institution
    Plasma Fusion Center, MIT, Cambridge, MA, USA
  • fYear
    1989
  • fDate
    2-6 Oct 1989
  • Firstpage
    769
  • Abstract
    The CIT will require a liquid-nitrogen-cooled, pulsed poloidal field coil system for plasma heating, shaping, and control. The central solenoid will have a bore diameter of 0.8 m, a height of 4.8 m, and a central field of 23-256 T. Geometric restrictions are such that an aggressive structure concept is required. Two options are being considered for the machine. The first would require a self-supporting central solenoid consisting of a stack of explosively bonded copper/Alloy-718 plates with a copper/Alloy-718 ratio of 50/50. Each plate is cut into eight turns by a water-jet cutting process. Features of this design are presented along with selected results from an R&D program under way. Full-scale plates have been fabricated and cut, and prototypical mechanical and electrical joints have been tested. The other machine design option would allow the central solenoid to receive partial support from the TF (toroidal field) coil system. In this case the operating scenario and stresses are substantially different. R&D tasks have been started to evaluate conductor lifetime under simulated operating conditions for alumina dispersion strengthened (ADS) copper. Explosively bonded copper/Alloy-718 plates remain an option, but with a substantial increase in the ratio of copper to Alloy 718 to 70/30. The status of test results and plans for these materials is given
  • Keywords
    fusion reactor materials; fusion reactor theory and design; Compact Ignition Tokamak; alumina dispersion strengthened Cu; bore diameter; central solenoid; conductor lifetime; control; electrical joints; mechanical joints; plasma heating; pulsed poloidal field coil; shaping; toroidal field coil system; water-jet cutting process; Bonding; Coils; Conducting materials; Copper alloys; Heating; Plasmas; Pulse shaping methods; Shape control; Solenoids; Temperature control;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 1989. Proceedings., IEEE Thirteenth Symposium on
  • Conference_Location
    Knoxville, TN
  • Type

    conf

  • DOI
    10.1109/FUSION.1989.102331
  • Filename
    102331