TEXTOR is a Tokamak Experiment for Technology Oriented Research in the field of plasma wall interaction. The scope not only includes a detailed analysis of particle and energy exchange between the plasma and the surrounding chamber but also involves active measures to optimize the first wall and the plasma boundary region in such a way that wall erosion, particle release and impurity influx to the plasma core are reduced to tolerable levels. In order to comply with these objectives TEXTOR has a number of special design features such as

• excellent access for diagnostics to domains near to the wall,
• large portholes suitable for implementing methods to control the plasma boundary,
• facilities to heat the vacuum vessel and the liner,
• provisions for exchange of the liner.

During several upgrades TEXTOR has been equipped with

• auxiliary heating systems (neutral beam injection, radio frequency heating, microwave heating),
• a toroidal pumped limiter,
• an upgraded magnetization coil, and recently
• the Dynamic Ergodic Divertor (DED).

TEXTOR Cross Section

1 DED coils, 2 Divertor tiles,
3 DED current feedthrough, 4 DED bus bar