• Title of article

    Treatment of ITER plasma facing components: Current status and remaining open issues before ITER implementation

  • Author/Authors

    Grisolia، نويسنده , , C. and Counsell، نويسنده , , G. and Dinescu، نويسنده , , G. and Semerok، نويسنده , , A. and Bekris، نويسنده , , N. and Coad، نويسنده , , P. and Hopf، نويسنده , , C. and Roth، نويسنده , , J. and Rubel، نويسنده , , M. and Widdowson، نويسنده , , A. and Tsitrone، نويسنده , , E.، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 2007
  • Pages
    9
  • From page
    2390
  • To page
    2398
  • Abstract
    The in-vessel tritium inventory control is one of the most ITER challenging issues which has to be resolved to fulfil safety requirements. This is due mainly to the presence of carbon as a constituent of plasma facing components (PFCs) which leads to a high fuel permanent retention. For several years now, physics studies and technological developments have been undertaken worldwide in order to develop reliable techniques which could be used in ITER severe environment (magnetic field, vacuum, high temperature) for in situ tritium recovery. The scope of this contribution is to review the present status of these achievements and define the remaining work to be done in order to propose a dedicated work program. ent treatment techniques (chemical treatments, photonic cleaning) will be reviewed. In the frame of ITER, they will be compared in terms of fuel removal rate as well as surface accessibility, type of production (gas or particulates), ability to clean mixed material. stly, consequences of bulk trapping observed in tokamak on the techniques currently under development will be addressed.
  • Keywords
    Detritiation techniques , Fuel cycle , ITER
  • Journal title
    Fusion Engineering and Design
  • Serial Year
    2007
  • Journal title
    Fusion Engineering and Design
  • Record number

    2354334