• DocumentCode
    1948406
  • Title

    Progress on the integration of ITER diagnostics equatorial port plugs in Europe

  • Author

    Salasca, S. ; Cantone, B. ; Dapena, M. ; Joanny, M. ; Aumeunier, MH ; Travere, JM ; Esposito, B. ; Moro, F. ; Marocco, D. ; Villari, R. ; Brolatti, G. ; Rincon, E. ; Varela, P. ; Nagy, D. ; Nemeth, J. ; Zeile, C. ; Perrollaz, G.

  • Author_Institution
    Inst. for Magn. Fusion Res., French Alternative Energies & Atomic Energy Comm., St. Paul-lez-Durance, France
  • fYear
    2011
  • fDate
    26-30 June 2011
  • Firstpage
    1
  • Lastpage
    6
  • Abstract
    Diagnostics in ITER are supported by big structures called port plugs, the second main function of which is to ensure a sufficient shielding against neutrons and gammas. Regarding the integration of diagnostics in equatorial port plugs, a new approach is under study, which consists in installing the diagnostics in “drawers”. This paper describes the recent work which has been performed in Europe on the integration of diagnostics in drawers in the Equatorial Port Plug 1 (EPP1). First the methodology which has been followed to progress on the integration of the diagnostics in this port plug is described and the resulting arrangement of diagnostics is shown. Then a special attention is paid to the integration of the two main diagnostics of EPP1, namely the visible/infrared wide angle viewing system and the radial neutron camera. Finally the preliminary design of the drawers of EPP1, in particular the shielding modules around the diagnostics, is presented, and the preliminary results of the analyses performed to validate this design are provided.
  • Keywords
    Tokamak devices; fusion reactor design; fusion reactor materials; plasma diagnostics; plasma toroidal confinement; shielding; EPP1; ITER diagnostics equatorial port plugs; equatorial port plug 1; infrared wide angle viewing system; radial neutron camera; shielding modules; visible wide angle viewing system; Bolometers; Flanges; Heating; Maintenance engineering; Plasmas; Plugs; Welding; ITER; diagnostics; integration; port plugs; shield modules;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering (SOFE), 2011 IEEE/NPSS 24th Symposium on
  • Conference_Location
    Chicago, IL
  • ISSN
    1078-8891
  • Print_ISBN
    978-1-4577-0669-1
  • Electronic_ISBN
    1078-8891
  • Type

    conf

  • DOI
    10.1109/SOFE.2011.6052255
  • Filename
    6052255