Surface morphology influence on deuterium retention in beryllium films prepared by thermionic vacuum arc method
In a plasma-confinement device, material eroded from plasma facing components will be
transported and re-deposited at other locations inside the reaction chamber. Since beryllium
from the first wall of the ITER fusion reactor will be eroded, ionized in the scrape-off layer
plasma and finally re-deposited on divertor surfaces flowing along the magnetic field, it is
important to study the properties of divertor armour materials (C, W) coated with beryllium.
By applying different bias voltages (− 200V to+ 700V) to the substrates during deposition …
transported and re-deposited at other locations inside the reaction chamber. Since beryllium
from the first wall of the ITER fusion reactor will be eroded, ionized in the scrape-off layer
plasma and finally re-deposited on divertor surfaces flowing along the magnetic field, it is
important to study the properties of divertor armour materials (C, W) coated with beryllium.
By applying different bias voltages (− 200V to+ 700V) to the substrates during deposition …
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