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(FT/P2-11) Application of a 1-D Predictive Model for Energy and Particle Transport to the Determination of ITER Plasma-SOL Interface Parameters

G.W. Pacher¹⁾, H.D. Pacher²⁾, A.S. Kukushkin³⁾, G. Janeschitz⁴⁾, G. Pereverzev^5)
 
1) Hydro-Québec (IREQ), V arennes, Canada
²⁾ INRS, Quebec, Canada
³⁾ ITER IT, Garching, Germany
⁴⁾ FZK-PL-Fusion, Karlsruhe, Germany
⁵⁾ Max-Planck-Institut für Plasmaphysik, EURATOM Assoc., Garching, Germany

Abstract.  The Integrated Core Pedestal Sol Model (ICPS Model) implemented in the 1.5D Astra code is applied to ITER conditions in order to obtain SOL interface parameters consistent with core operation. Because transport in the model is reduced by a combination of magnetic and electric field shear, the initial operating point after density and power rampup depends on the details of the rampup scenario, since the initial current distribution is ``frozen in'' and relaxes over hundreds of seconds. In the scenarios investigated, the initial magnetic shear after rampup is higher than for the fully relaxed state, so that transiently the confinement time and Q are larger than obtained in steady state. This relaxation and the control strategy to obtain an acceptable time dependence of power flow into the scrape-off layer are investigated for operating scenarios typical of ITER conditions. Operating conditions consistent with both core and edge requirements for input to the 2-D modelling of the divertor/SOL are obtained by systematic variations of edge fuelling, heating power, core fuelling penetration, edge helium concentration, and radiation fraction.

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