Erosion and redeposition at the vessel walls in fusion devicesFunded under: EAEC-FUSION 12C
The plasma induced erosion and redeposition at the vessel walls in fusion devices have been investigated both with the computer simulation code ERO, and in experiments. Well prepared carbon probes with implanted and evaporated markers in the surface layers have been exposed in the scrape-off layer (SOL) of several tokamaks such as JET, TEXTOR and ASDEX-Upgrade. The main plasma parameters are simultaneously determined. After exposure to single plasma discharges, erosion and redeposition of the marker material were measured by surface layer analysis with MeV ion beam techniques. The experimental results were compared with the results from the ERO code.
Bibliographic Reference: Article: Journal of Nuclear Materials, Vols. 220-222 (1995) pp. 227-230
Record Number: 199510929 / Last updated on: 1995-08-10
Original language: en
Available languages: en