Interactions between the plasma and the vessel walls constitute a major engineering
problem for next step fusion devices, such as ITER, determining the choice of the plasma …

Recent research in scrape-off layer (SOL) and divertor physics is reviewed; new and existing
data from a variety of experiments have been used to make cross-experiment comparisons …

Net erosion and deposition of tungsten (W) in the ASDEX Upgrade divertor were determined
after the 2007 campaign by using thin W marker stripes. ASDEX Upgrade had full-W plasma …

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 …

Tungsten is currently the most promising material for plasma-facing in FRs. The
accumulation of radioactive tritium in tungsten is caused by presence of hydrogen traps in …

The erosion of tungsten and carbon marker layers was studied in the outer divertor of
ASDEX Upgrade. The outer strike point area and a large fraction of the outer baffle are net …

Divertor and midplane material evaluation systems (DiMES and MiMES) in the DIII-D
tokamak are used to address a variety of plasma–material interaction (PMI) issues relevant …

The number of ionization events per photon, ie S/XB value, of Mo I lines has been
determined by taking a ratio of the sputtered Mo flux, Γ Spt Mo, to the line-of-sight integrated …

The deuterium inventory in ASDEX Upgrade was determined by quantitative ion beam
analysis techniques and SIMS for different discharge campaigns between the years 2002 …

The migration of carbon in low-density, low-confinement plasmas of ASDEX Upgrade was
studied by injecting 13 C into the main chamber of the torus at the end of the 2007 …