Mainz 2022 – wissenschaftliches Programm
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P: Fachverband Plasmaphysik
P 12: Magnetic Confinement / Plasma Wall Interaction I
P 12.5: Vortrag
Mittwoch, 30. März 2022, 15:00–15:15, P-H12
Investigation of hydrogen retention in beryllium and beryllium-tungsten alloys — •Meike Flebbe, Timo Dittmar, and Christian Linsmeier — FZJ, Jülich, Germany
ITER will use beryllium (Be) as first wall material and tungsten (W) as divertor material. Alloys can form due to erosion of beryllium and tungsten particles and their redeposition elsewhere. In the course of the plasma-wall interaction, tritium from the plasma can be deposited in the plasma facing material. For safety and for tritium breeding and economy considerations, the understanding of hydrogen retention in Be-W-alloys is of central importance for the fusion research in order to be able to realize a fusion reactor.
Fundamental experiments are required to understand the processes involved in hydrogen retention in Be-W-alloys. These can be executed with the help of in-situ ion beam experiments. A suitable system for this is ARTOSS, a high vacuum device from the FZJ, in which Be-W-alloys can be produced, loaded with deuterium and examined using analysis diagnostics like thermal desorption spectroscopy (TDS) and ion beam analysis (IBA). Recent studies have shown a low temperature desorption peak at around 400 K for beryllium, which shows a splitting into a fine structure from a threshold fluence of 1 · 1021 m−2 with a sufficiently high resolution. The mechanism behind this split is still unknown. To test whether hydrides are the reason for the fine structure, ramp-and-hold TDS experiments are used.
In this contribution, I will show results from previous studies and give an outlook on ramp-and-hold experiments with beryllium.