At the central column of ASDEX Upgrade, an area of 5.5 m(2) of graphite tiles was replaced by tungsten-coated tiles representing about two-thirds of the total area of the central column. No negative influence on the plasma performance was found, except for internal transport barrier limiter discharges. The tungsten influx Gamma(W) stayed below the detection limit only during direct plasma wall contact or for reduced clearance in divertor discharges spectroscopic evidence for Gamma(W) could be found. From these observations a penetration factor of the order of 1% and effective sputtering yields of about 10(-3) could be derived, pointing to a strong contribution by light intrinsic impurities to the total W- sputtering. The tungsten concentrat...
Net erosion and deposition of tungsten (W) in the ASDEX Upgrade divertor were determined after the 2...
The WEST experiment is currently operating with tungsten plasma-facing components and testing ITER-l...
ASDEX Upgrade was operated with about 6400 s plasma discharge during the scientific program in 2007/...
At the central column of ASDEX Upgrade, an area of 5.5 m(2) of graphite tiles was replaced by tungst...
Since 1998 an increasing area of tungsten coated tiles has been installed at the central column of ...
In ASDEX Upgrade, the transition from carbon based plasma facing components towards a full tungsten ...
The tungsten programme in ASDEX Upgrade is pursued towards a full high-Z device. The spectroscopic d...
In the all W ASDEX Upgrade impurities are injected routinely for radiative cooling. Amongst the diff...
ASDEX Upgrade has recently finished its transition towards an all-W divertor tokamak, by the exchang...
In ASDEX Upgrade tungsten is used as a high-Z plasma facing material. Its erosion, migration and sub...
Abstract. The material for plasma facing components of a future fusion device is still not decided. ...
Abstract In ASDEX Upgrade, nearly all plasma facing components (PFC) besides the strike point area o...
Impurity behaviour in advanced scenarios at ASDEX Upgrade and JET has been investigated. For ASDEX U...
Currently 85 % of the plasma facing components of ASDEX Upgrade are tungsten coated. Carbon inux fro...
Abstract Operation with all tungsten plasma facing components has become routine in ASDEX Upgrade. T...
Net erosion and deposition of tungsten (W) in the ASDEX Upgrade divertor were determined after the 2...
The WEST experiment is currently operating with tungsten plasma-facing components and testing ITER-l...
ASDEX Upgrade was operated with about 6400 s plasma discharge during the scientific program in 2007/...
At the central column of ASDEX Upgrade, an area of 5.5 m(2) of graphite tiles was replaced by tungst...
Since 1998 an increasing area of tungsten coated tiles has been installed at the central column of ...
In ASDEX Upgrade, the transition from carbon based plasma facing components towards a full tungsten ...
The tungsten programme in ASDEX Upgrade is pursued towards a full high-Z device. The spectroscopic d...
In the all W ASDEX Upgrade impurities are injected routinely for radiative cooling. Amongst the diff...
ASDEX Upgrade has recently finished its transition towards an all-W divertor tokamak, by the exchang...
In ASDEX Upgrade tungsten is used as a high-Z plasma facing material. Its erosion, migration and sub...
Abstract. The material for plasma facing components of a future fusion device is still not decided. ...
Abstract In ASDEX Upgrade, nearly all plasma facing components (PFC) besides the strike point area o...
Impurity behaviour in advanced scenarios at ASDEX Upgrade and JET has been investigated. For ASDEX U...
Currently 85 % of the plasma facing components of ASDEX Upgrade are tungsten coated. Carbon inux fro...
Abstract Operation with all tungsten plasma facing components has become routine in ASDEX Upgrade. T...
Net erosion and deposition of tungsten (W) in the ASDEX Upgrade divertor were determined after the 2...
The WEST experiment is currently operating with tungsten plasma-facing components and testing ITER-l...
ASDEX Upgrade was operated with about 6400 s plasma discharge during the scientific program in 2007/...