Treatment of ITER Plasma Facing Components current status et remaining open issues before ITER implementation

C. Grisolia , G. Counsell , G. Dinescu (1) , A. Semerok (2) , N. Bekris , P. Coad , C. Hopf (3) , J. Roth (3) , M. Rubel , . Widdowson A

1 NILPRP
2 CEA-DES (ex-DEN) - CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire)
3 IPP - Max-Planck-Institut für Plasmaphysik [Garching]

The in vessel tritium inventory control is one of the most ITER challenging issues which has to be performed 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 presentation 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.Different treatment techniques (chemical treatments, photonic cleaning) will be reviewed. In the frame of ITER, they will be compared in term of fuel removal efficiency as well surface accessibility, type of production (gas or particulates), ability to clean mixed material. Ad last, consequences of bulk trapping observed in tokamak on the techniques currently under development will be addressed.

Mots clés: Tokamak; fusion; detritiation; ITER

Domaines: Physique Nucléaire Expérimentale [nucl-ex]; Physique Nucléaire Théorique [nucl-th]

C. Grisolia, G. Counsell, G. Dinescu, A. Semerok, N. Bekris, et al.. Treatment of ITER Plasma Facing Components current status et remaining open issues before ITER implementation. Fusion Engineering and Design, 2007, 82, ⟨10.1016/j.fusengdes.2007.05.047⟩. ⟨cea-02355369⟩