Author/Authors :
Federici، نويسنده , , G. and Andrew، نويسنده , , P. and Barabaschi، نويسنده , , P. and Brooks، نويسنده , , J. and Doerner، نويسنده , , R. and Geier، نويسنده , , A. and Herrmann، نويسنده , , A. and Janeschitz، نويسنده , , G. and Krieger، نويسنده , , K. and Kukushkin، نويسنده , , A. and Loarte، نويسنده , , A. and Neu، نويسنده , , R. and Saibene، نويسنده , , G. and Shimada، نويسنده , , M. and Strohmayer، نويسنده , , G. and Sugihara، نويسنده , , M، نويسنده ,
Abstract :
Some of the remaining crucial plasma edge physics and plasma–material interaction issues of the ITER tokamak are discussed in this paper, using either modelling or projections of experimental results from existing tokamak operation or relevant laboratory simulations. The paper covers the following subject areas at issue in the design of the ITER device: (1) plasma thermal loads during Type I ELMs and disruptions, ensuing erosion effects and prospects for mitigating measures, (2) control of co-deposited tritium inventory when carbon is used even on small areas in the divertor near the strike points, (3) efficiency of edge and core fuelling for expected pedestal densities in ITER, and (4) erosion and impurity transport with a full tungsten divertor. Directions and priorities of future research are proposed to narrow remaining uncertainties in the above areas.
Keywords :
Plasma-edge physics , ITER , B2-EIRENE code , Divertor , Boundary plasmas , Plasma–wall interaction
