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Experimental conditions concerning magnetic configurations, heating scenarios and density control for generating high ion temperatures and high beta in W7-AS are described and experimental results are compared with theoretical predictions. Ion temperatures of up to 1.5 keV, the highest in helical systems so far, have been achieved. Energy confinement times about twice as long as predicted by the International Stellarator Scaling are derived for these discharges. This improvement is clearly related to the steep temperature and density gradients in the outer part of the plasma. In the bulk part, the experimental particle and energy fluxes as well as the radial electric field, E(r), are well consistent with neoclassical calculations, but a discrepancy is found for E(r) in the gradient region of the profiles, whereas at the outermost part the agreement is good again. The strongly negative E(r) in the profile gradient region forms a transport barrier with respect to the ion channel. Both sufficient high ion heating and low anomalous particle fluxes at the outer radii (ie low recycling) are mandatory for establishing this strongly negative E(r). The effect of this poloidal plasma rotation on the edge turbulence and confinement may be quite similar to that in tokamaks.

Additional information

Authors: KICK M ET AL, Max-Planck-Institut für Plasmaphysik, Garching bei München (DE);KISLYAKOV A I, A F Ioffe Physico-Technical Institute, St Petersburg (RU)
Bibliographic Reference: Article: Fusion Energy 1996; proceedings of the sixteenth international conference, Vol. 2 (1997) pp. 27-39
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