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(CT/P-07) ITER Divertor Plasma Modelling with Consistent Core-Edge Parameters

A.S. Kukushkin¹⁾, H.D. Pacher²⁾, G.W. Pacher³⁾, G. Janeschitz⁴⁾, D. Coster⁵⁾, A. Loarte⁶⁾, D. Reiter^7)
 
1) ITER IT, ITER Garching JWS, Garching, Germany;
²⁾ INRS-EMT, Varennes, Québec, Canada
³⁾ Hydro-Québec, Varennes, Québec, Canada
⁴⁾ FZK-PL-Fusion, Karlsruhe, Germany
⁵⁾ Max-Planck-Institut für Plasmaphysik, Garching, Germany
⁶⁾ EFDA, Garching, Germany
⁷⁾ FZ Jülich, Jülich, Germany

Abstract.  The latest results of divertor modelling for ITER are presented in the paper. The effect of core fuelling, which is needed to sustain the necessary density gradient in the ``pedestal'' region just inside the separatrix (and which produces higher plasma outflow across the separatrix), on the divertor performance is studied. Flexibility of the ITER divertor geometry for the density control is assessed, and a feasibility and limits of the separatrix density control via adjusting the separatrix strike point position on the target are studied. Issues of impurity mixing due to erosion and deposition of plasma-facing component materials are also addressed.

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