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(FT/P2-12) Control of the Plasma Fluxes into the Divertor Region of the Tokamak KTM

A.D. Barkalov1), E.A. Azizov1), G.G. Gladush1), V.N. Dokuka1), N.A. Obysov2), Yu.M. Semenets1), R.R. Khayrutdinov1)
1) TRINITI, Troitsk, Moscow region, Russia
2) Minatom of RF, Moscow, Russia

Abstract.  The Kazakhstan Tokamak for Material studies (KTM) being under construction now is dedicated for extensive investigations of the plasma facing components in the conditions of ITER and future fusion reactors. The problem of the control of the plasma fluxes into the divertor region and onto the target plates is especially important for this device. In the present paper, various factors determining the structure and the values of such fluxes are analyzed. The main factors are the additional heating power and the plasma current. The additional heating power determines the SOL width and the SOL broadening at the divertor plates is determined by the plasma current. Using the ITER scalings and the numerical code DINA it is shown that the pick power at the divertor plates can change in a wide region including the pick loads of ITER. The influence of the x-point sweeping, the vertical displacement of the divertor table, ELMs and VDE are also considered.

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IAEA 2003