• DocumentCode
    324979
  • Title

    ITER tokamak dust-limits, production, removal, surveying

  • Author

    Piet, S.J. ; Costley, A. ; Federici, G. ; Heckendorn, F. ; Little, R.

  • Author_Institution
    Nat. Eng. & Environ. Lab., Idaho Falls, ID, USA
  • Volume
    1
  • fYear
    1997
  • fDate
    6-10 Oct 1997
  • Firstpage
    167
  • Abstract
    Some tokamak dust will exist inside the ITER Vacuum Vessel as a result of routine sputtering, disruptions, and possibly maintenance related activities. The three plasma-facing materials (beryllium, carbon, tungsten) will give rise to a dust mixture with radiological, chemically toxic, and chemically reactive hazards. The project has evolved an approach to ensuring that the public is protected via confinement, limiting chemical reactions, and limiting the dust inventory. This paper provides an overview of the dust safety limits, production, removal, and surveying methods
  • Keywords
    beryllium; carbon; dust; fusion reactor safety; tungsten; Be; C; ITER; Vacuum Vessel; W; chemical reactions; dust; dust inventory; dust removal; plasma-facing materials; safety; surveying; Chemical hazards; Dusty plasma; Hazardous materials; Plasma chemistry; Plasma confinement; Plasma materials processing; Production; Sputtering; Tokamaks; Toxic chemicals;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 1997. 17th IEEE/NPSS Symposium
  • Conference_Location
    San Diego, CA
  • Print_ISBN
    0-7803-4226-7
  • Type

    conf

  • DOI
    10.1109/FUSION.1997.687012
  • Filename
    687012