• DocumentCode
    2759523
  • Title

    Shielding Design of ITER Pressure Suprression System

  • Author

    Yamauchi, M. ; Sato, S. ; Nishitani, T. ; Kawasaki, H.

  • Author_Institution
    Japan Atomic Energy Res. Inst., Ibaraki
  • fYear
    2005
  • fDate
    Sept. 2005
  • Firstpage
    1
  • Lastpage
    4
  • Abstract
    Pressure relief lines are installed to cope with the unexpected in-vessel pressurization due to LOCA in the vacuum vessel of ITER. Since neutrons stream through the line, it must be designed so that the activation of components in the line is low enough for the maintenance work. Several designs of the pressure relief lines were studied with a simple design code DUCT-III, and the reasonable condition for the duct size, number of bends and the lengths of the legs were estimated to suppress the activation of the rupture disc. On the other hand, neutron permeation from the first to the second or third leg through the duct shield may also enhance the activation. The permeation was studied by Monte Carlo calculations with MCNP code, and 0.15 m thick iron shield was estimated enough to suppress the permeating neutrons. In addition, the volume of the shield may be reduced by about 30% if the optimized iron shield structure having localized thickness against the intense permeation path is employed
  • Keywords
    Monte Carlo methods; Tokamak devices; fusion reactor design; fusion reactor materials; ITER pressure suppression system; LOCA; MCNP code; Monte Carlo calculation; duct shield; duct size; intense permeation path; neutron permeation; neutrons stream; optimized iron shield structure; pressure relief lines; rupture disc; shielding design; simple design code DUCT-III; unexpected in-vessel pressurization; vacuum vessel; Cyclic redundancy check; Design methodology; Ducts; Elementary particle vacuum; Iron; Leg; Monte Carlo methods; Neutrons; Performance analysis; Vacuum systems; ITER; Monte Carlo code MCNP; component; neutron shield; neutron streaming; pressure relief line; radio-activation; rupture disc; simple design code DUCT-III;
  • 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.2005.252902
  • Filename
    4018936