• DocumentCode
    2758995
  • Title

    The ITER Central Solenoid

  • Author

    Schultz, Joel H. ; Antaya, Timothy ; Feng, Jun ; Gung, Chen-Yu ; Martovetsky, Nicolai ; Minervini, Joseph V. ; Michael, Philip ; Radovinsky, Alexi ; Titus, Peter

  • Author_Institution
    Plasma Sci. & Fusion Center, MIT, Cambridge, MA
  • fYear
    2005
  • fDate
    Sept. 2005
  • Firstpage
    1
  • Lastpage
    4
  • Abstract
    The central solenoid for the International Thermonuclear Experimental Reactor (ITER), a fusion tokamak experiment with the goal of generating 500 MW of fusion power with high gain (Q>10), must provide most of the volt-seconds needed to induce and sustain a 15 MA plasma for burn times of >400 s. The 6.4 GJ central solenoid design requires a 45 kA conductor and has a peak field of 13 T. The central solenoid consists of six pancake-wound modules, stacked vertically, and held in axial compression by an external structure. The five-stage cable has 1/3 copper and 2/3 advanced Nb3Sn strands in a thick superalloy conduit and is cooled by the forced-flow of supercritical helium through the cable space. Key design issues include the qualification of a conduit with adequate fatigue strength, avoiding filament damage from transverse Lorentz loads, eliminating axial tension in the winding insulation, and qualification of space-saving intramodule butt joints
  • Keywords
    Tokamak devices; fatigue; fusion reactor design; solenoids; superconducting cables; superconducting magnets; 1/3 copper strands; 2/3 advanced Nb3Sn strands; ITER central solenoid; International Thermonuclear Experimental Reactor; axial tension elimination; fatigue strength; filament damage; five-stage cable; fusion power; fusion tokamak experiment; six pancake-wound modules; space-saving intramodule butt joints; superconducting magnets; supercritical helium forced-flow; thick superalloy conduit; transverse Lorentz loads; winding insulation; Conductors; Copper; Fusion power generation; Fusion reactor design; Inductors; Plasmas; Power generation; Qualifications; Solenoids; Tokamaks; ITER; cable in conduit; fusion reactors; superconducting magnets; superconductors;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering 2005, Twenty-First IEEE/NPS Symposium on
  • Conference_Location
    Knoxville, TN
  • Print_ISBN
    0-4244-0150-X
  • Electronic_ISBN
    0-4244-0150-X
  • Type

    conf

  • DOI
    10.1109/FUSION.2005.252874
  • Filename
    4018908