Tungsten as target material in fusion devices

D. Naujoks, K. Asmussen, M. Bessenrodt-Weberpals, S. Deschka, R. Dux, W. Engelhardt, A. R. Field, G. Fussmann, J. C. Fuchs, C. García-Rosales, S. Hirsch, P. Ignacz, G. Lieder, K. F. Mast, R. Neu, R. Radtke, J. Roth, U. Wenzel

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Several experiments were conducted in ASDEX Upgrade to prove the suitability of tungsten as a divertor target material under the conditions of a high density and low temperature divertor. The observed fluxes from a tungsten tile into the plasma are low, in keeping with the extremely low sputtering yields. In addition, the very favourable effect of 'prompt redeposition' (redeposition during the first gyration) could be confirmed by the experiments. Cooling of the edge region by neon injection seems permissible, i.e. neon impurity sputtering did not increase the eroded fluxes of tungsten. The transport and accumulation behaviour were investigated by means of the laser blow-off technique. No accumulation effects could be observed in ohmic discharges. In discharges with NBI heating but without ICRH, strong accumulation can occur. High heat flux tests were performed on graphite tiles coated with plasma sprayed tungsten, which withstood a thermal load of 15 MW/m2 lasting 2s as well as 1000 cycles of 10 MW/m2 for 2s without disabling damage. Owing to the encouraging results, an experiment using a tungsten divertor is planned in ASDEX Upgrade.

Original languageEnglish
Pages (from-to)671-687
Number of pages17
JournalNuclear Fusion
Issue number6
StatePublished - Jun 1996
Externally publishedYes


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