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Experimental observations and some preliminary results from B2-Eirene code modelling of divertor detachment in the TCV tokamak are reported, with emphasis on the aspects of this detachment related to divertor geometry. The contribution is restricted to deuterium fuelled ohmic plasmas for which the CB drift is directed away from the X-point of lower single-null, open diverted equilibria with fixed elongation and triangularity. Unlike more conventional diverted equilibria, however, the configurations described are characterised by both a very short divertor poloidal depth on a vertical target and a very long poloidal depth on a horizontal target. Results are presented from density ramp discharges in which the outer (high poloidal depth) divertor is already in the high recycling regime at the start of the density ramp and in which varying degrees of detachment are obtained depending on the magnitude of the imposed outer divertor flux expansion. In contrast, the inner divertor remains in the large Dart attached for all densities. (C) 2001 Elsevier Science B.V. All rights reserved.
Basil Duval, Holger Reimerdes, Christian Gabriel Theiler, Joaquim Loizu Cisquella, Artur Perek, Guang-Yu Sun, Sophie Danielle Angelica Gorno, Claudia Colandrea, Luke Simons, Garance Hélène Salomé Durr-Legoupil-Nicoud, Davide Galassi, Lorenzo Martinelli, Curdin Tobias Wüthrich
Sophie Danielle Angelica Gorno