Wall conditioning is essential in tokamak and stellarator research to achieve plasma
performance and reproducibility. This paper presents an overview of recent conditioning …

The Wendelstein 7-X project is aimed at demonstrating that an optimised stellarator is an
attractive candidate for a fusion reactor. This requires the achievement of a number of …

W7-X completed its plasma operation in hydrogen with island divertor and inertially cooled
test divertor unit (TDU) made of graphite. A substantial set of plasma-facing components …

A set of dedicated marker samples consisting of fine-grain graphite as substrate, an
interlayer of 0.2–0.4 μm molybdenum (Mo) employed as marker, and a 5–10 μm thick …

The net erosion and deposition pattern of carbon from the Test Divertor Unit (TDU) of the
stellarator W7-X was determined. Special target elements with marker layers consisting of …

Abstract Wendelstein 7-X (W7-X) is an optimized stellarator with a 3-dimensional five-fold
modular geometry. The plasma-wall-interaction (PWI) investigations in the complex 3D …

Carbon net erosion and deposition at the test divertor unit (TDU) of Wendelstein 7-X (W7-X)
were measured for the discharge period OP 1.2 b in the year 2018 using 18 specially …

The W7-X stellarator has so far performed experiments under both limiter and divertor
conditions. The plasma is mostly generated by ECR-heating with powers up to 6.5 MW, and …

Distributions of deposits and hydrogen (H) on the graphite divertor target elements TM4h4
and TM3v5 in the test divertor units 3 (TDUs3) of Wendelstein 7-X (W7-X) are studied. The …

Detached divertor plasmas has been achieved by density ramp in W7-X. During the
transition into detachment, the main divertor radiation region moves from the region close to …