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Tungsten as target material in fusion devices

Authors :
S. Deschka
W. Engelhardt
G. Lieder
R. Radtke
Carmen García-Rosales
Dirk Naujoks
M. Bessenrodt-Weberpals
P. Ignacz
K. Asmussen
G. Fussmann
K. F. Mast
R. Dux
J. Roth
S. Hirsch
A. R. Field
Rudolf Neu
Julia Fuchs
U. Wenzel
Source :
Nuclear Fusion. 36:671-687
Publication Year :
1996
Publisher :
IOP Publishing, 1996.

Abstract

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 2 s as well as 1000 cycles of 10 MW/m2 for 2 s without disabling damage. Owing to the encouraging results, an experiment using a tungsten divertor is planned in ASDEX Upgrade

Details

ISSN :
00295515
Volume :
36
Database :
OpenAIRE
Journal :
Nuclear Fusion
Accession number :
edsair.doi...........d6a41a56e6263ef8bb1c19a760306790
Full Text :
https://doi.org/10.1088/0029-5515/36/6/i01