Experiments dealing with plasma-wall interactions and first-wall materials comprise a significant part of the work program of ASDEX Upgrade. To elucidate carbon chemical erosion under reactor-relevant conditions, dedicated spectroscopic measurements were performed. These investigations are complemented with long-term erosion and deposition probes consisting of various materials, which are mounted at numerous locations inside the vacuum vessel. The codeposition of hydrogen with carbon below the divertor is studied in detail with long-term samples as well as with quartz microbalance measurements, which allow a discharge-resolved measurement of the layer growth. In parallel to the investigations on carbon, the behavior of tungsten plasma facin...
Abstract. The effect of surface roughness on the long-term erosion patterns of tungsten coatings was...
Net erosion and deposition of tungsten (W) in the ASDEX Upgrade divertor were determined after the 2...
The key problem for the use of carbon in a future fusion device is the formation of tritium containi...
Experiments dealing with plasma-wall interactions and first-wall materials comprise a significant pa...
Abstract. The material for plasma facing components of a future fusion device is still not decided. ...
Plasma-wall interactions have been studied in the full-W ASDEX Upgrade during its dedicated helium c...
The erosion of tungsten and carbon marker layers was studied in the outer divertor of ASDEX Upgrade....
In ASDEX Upgrade, tungsten is employed as plasma facing material at the central column of the plasma...
ASDEX Upgrade has recently finished its transition towards an all-W divertor tokamak, by the exchang...
During the campaign 2002–2003 a carbon erosion and deposition experiment was performed in the lower ...
In ASDEX Upgrade, tungsten was employed as plasma facing material at the central column heat shield ...
Abstract In ASDEX Upgrade, nearly all plasma facing components (PFC) besides the strike point area o...
The influence of the transition of the plasma facing components (PFC) from carbon (C) to tungsten (W...
| openaire: EC/H2020/633053/EU//EUROfusionGross and net erosion of tungsten (W) and other plasma-fac...
In ASDEX Upgrade tungsten is used as a high-Z plasma facing material. Its erosion, migration and sub...
Abstract. The effect of surface roughness on the long-term erosion patterns of tungsten coatings was...
Net erosion and deposition of tungsten (W) in the ASDEX Upgrade divertor were determined after the 2...
The key problem for the use of carbon in a future fusion device is the formation of tritium containi...
Experiments dealing with plasma-wall interactions and first-wall materials comprise a significant pa...
Abstract. The material for plasma facing components of a future fusion device is still not decided. ...
Plasma-wall interactions have been studied in the full-W ASDEX Upgrade during its dedicated helium c...
The erosion of tungsten and carbon marker layers was studied in the outer divertor of ASDEX Upgrade....
In ASDEX Upgrade, tungsten is employed as plasma facing material at the central column of the plasma...
ASDEX Upgrade has recently finished its transition towards an all-W divertor tokamak, by the exchang...
During the campaign 2002–2003 a carbon erosion and deposition experiment was performed in the lower ...
In ASDEX Upgrade, tungsten was employed as plasma facing material at the central column heat shield ...
Abstract In ASDEX Upgrade, nearly all plasma facing components (PFC) besides the strike point area o...
The influence of the transition of the plasma facing components (PFC) from carbon (C) to tungsten (W...
| openaire: EC/H2020/633053/EU//EUROfusionGross and net erosion of tungsten (W) and other plasma-fac...
In ASDEX Upgrade tungsten is used as a high-Z plasma facing material. Its erosion, migration and sub...
Abstract. The effect of surface roughness on the long-term erosion patterns of tungsten coatings was...
Net erosion and deposition of tungsten (W) in the ASDEX Upgrade divertor were determined after the 2...
The key problem for the use of carbon in a future fusion device is the formation of tritium containi...