Abstract
Tungsten coated graphite tiles were mounted in the divertor of the ASDEX Upgrade tokamak and exposed to approximately 800 plasma discharges. After the experimental campaign, a poloidally complete set of samples was removed. The poloidal tungsten distribution pattern is presented and compared to those of other metallic impurities. The amount of tungsten detected on main chamber plasma facing components is found to be nearly unaffected by the operation of a fully tungsten covered divertor. Modifications of the tungsten surfaces are analyzed. Deposition is observed to dominate in the inner divertor while erosion prevails in the outer divertor. The influence of this result on the target plate deuterium inventories is demonstrated. Finally, a model description for the deuterium inventories observed in the main chamber is presented.
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