• DocumentCode
    1071107
  • Title

    Design of the high-Tc superconducting TF coil for the tight aspect ratio Tokamak power reactor (VECTOR)

  • Author

    Ando, Toshinari ; Nishio, Satoshi ; Yoshimura, Hideto

  • Author_Institution
    Japan Atomic Energy Res. Inst., Ibaraki, Japan
  • Volume
    14
  • Issue
    2
  • fYear
    2004
  • fDate
    6/1/2004 12:00:00 AM
  • Firstpage
    1481
  • Lastpage
    1484
  • Abstract
    The tight aspect ratio tokamak power reactor (VECTOR) is proposed as a compact fusion reactor in a cost-effective way at JAERI. In the coil system, a center solenoid is discarded from the inner side of the plasma to realize low aspect configuration and the TF coil inner leg side is a solid-like integrated center post structure. The toroidal field (TF) coil consists of 12 D-shaped coil units whose inner bores are 12 m in height and 6 m in width. The magnetic field at the plasma center is designed to be 5 T. The maximum field in winding of the TF coil is required to be 18.3 T because of low aspect ratio. The magnetic stored energy is 10.7 GJ much less than the 40 GJ for ITER. For such high field generation and high performance coil realization, a high Tc superconductor is applied to the TF coil. The coil operating current is 178 kA at 18.3 T. The structure of the TF coil unit is composed of 5 radial plates and 2 support plates unified through bolts without coil case. The radial plates are designed with "beak type" structure that its inner leg part is bent to attain high current density in winding. The conductor that is composed of high Tc superconductor strands impregnated with lead, is inserted into grooves of the radial plates. The lead plays an important role on solidification of the strands cabled and on enthalpy stabilization with its high heat capacity. For the high Tc material, Bi2212 is chosen. The operating temperature of the conductor is 20 K. The conductor is cooled indirectly from cooling plates provided between the radial plates. The conductor has the temperature margin of 3 K proofed against disturbance of 1 J/cc at 20 K.
  • Keywords
    Tokamak devices; bismuth compounds; cooling; fusion reactor design; high-temperature superconductors; magnetic fields; plates (structures); superconducting coils; winding (process); 10.7 GJ; 12 m; 178 kA; 18.3 T; 20 K; 5 T; 6 m; Ba2Sr2CaCu2O8; Bi2212; D-shaped coil units; JAERI; VECTOR; aspect ratio; center solenoid discarding; coil operating current; coil winding; conductor operating temperature; cooling plates; enthalpy stabilization; fusion reactor; high Tc material; high current density; high-Tc superconductor; lead impregnation; magnetic field; magnetic stored energy; plasma center; radial plates; superconducting TF coil; superconductor strands; support plates; tokamak power reactor; toroidal field coil; Conducting materials; Fusion reactor design; Fusion reactors; Inductors; Leg; Plasma temperature; Superconducting cables; Superconducting coils; Tokamaks; Toroidal magnetic fields; Fusion reactor; VECTOR; high $rm T_rm c$ superconductor; toroidal field coil;
  • fLanguage
    English
  • Journal_Title
    Applied Superconductivity, IEEE Transactions on
  • Publisher
    ieee
  • ISSN
    1051-8223
  • Type

    jour

  • DOI
    10.1109/TASC.2004.830659
  • Filename
    1325078