Tungsten as target material in fusion devices
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 (ie 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 15MW/m(2) lasting 2 s as well as 1000 cycles of 10 MW/m(2) for 2 s without disabling damage. Owing to the encouraging results, an experiment using a tungsten divertor is planned in ASDEX Upgrade.
Bibliographic Reference: Article: Nuclear Fusion, Vol. 36 (1996) No. 6, pp. 671-687
Record Number: 199611021 / Last updated on: 1996-09-30
Original language: en
Available languages: en