Affordable Access

Publisher Website

Deuterium retention in tungsten oxide under low energy [formula omitted]plasma exposure

Journal of Nuclear Materials
Publication Date
DOI: 10.1016/j.jnucmat.2009.01.191


Abstract W is a candidate for plasma facing material and oxide layers are highly anticipated on W surface. We have studied deuterium (D) retention in tungsten oxide (WO 3) films and thermal release of deuterium. WO 3 films, prepared by oxidation of W metal sheet, were exposed to D 2 plasma under AC glow discharge at the applied voltage V up to a few kV and DC discharge. D-retention in W has been studied for comparison. The amount of D retained in the WO 3 films and W were analyzed by detecting α particles from the nuclear reaction, D( 3He, α)p, using 0.7 MeV 3He + ions. We find that D-uptake in WO 3 film is much larger than in W. According to thermal desorption, release of D 2 occurs at ∼180 and 450 °C.

There are no comments yet on this publication. Be the first to share your thoughts.


Seen <100 times

More articles like this

Characteristic changes of deuterium retention on t...

on Journal of Nuclear Materials Jan 01, 2005

Surface morphology and deuterium retention in tung...

on Journal of Nuclear Materials Jan 01, 2011

Deuterium retention in plasma spray tungsten coati...

on Journal of Nuclear Materials Jan 01, 2011

Temperature dependence of blistering and deuterium...

on Fusion Engineering and Design Jan 01, 2008
More articles like this..