• DocumentCode
    2080736
  • Title

    Shielding design options for the TF magnets of ITER

  • Author

    El-Guebaly, Laila A.

  • Author_Institution
    Fusion Technol. Inst., Wisconsin Univ., Madison, WI, USA
  • fYear
    1989
  • fDate
    2-6 Oct 1989
  • Firstpage
    1329
  • Abstract
    Optimization studies performed to design an efficient shield to protect the toroidal-field (TF) magnets of the International Thermonuclear Experimental Reactor (ITER) are described. Several options for the shield design were examined and many shielding materials have been evaluated. The pure stainless steel/H2O shield does not satisfy the magnet radiation limits. When boron carbide, lead, or boron steel is incorporated in the shield, all design limits are met. The midplane of the inner legs and the top and bottom parts of the magnets suffer the greatest damage because of the limited space for the shield. The safety factors associated with the different magnet responses were quantified. These factors account for the increase in damage due to the presence of the assembly gaps between the shield modules and the uncertainties in data, codes, and modeling
  • Keywords
    Tokamak devices; boron compounds; electromagnets; fusion reactor materials; fusion reactor safety; fusion reactor theory and design; lead; shielding; stainless steel; B4C; H2O; ITER; International Thermonuclear Experimental Reactor; Pb; assembly gaps; safety factors; shield; stainless steel; toroidal field magnets; Assembly; Boron; Design optimization; Inductors; Leg; Magnetic materials; Magnets; Protection; Radiation safety; Steel;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 1989. Proceedings., IEEE Thirteenth Symposium on
  • Conference_Location
    Knoxville, TN
  • Type

    conf

  • DOI
    10.1109/FUSION.1989.102456
  • Filename
    102456