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@ARTICLE{Houben:888658,
author = {Houben, A. and Scheuer, J. and Rasiński, M. and Kreter, A.
and Unterberg, B. and Linsmeier, Ch.},
title = {{H}ydrogen permeation and retention in deuterium plasma
exposed 316{L} {ITER} steel},
journal = {Nuclear materials and energy},
volume = {25},
issn = {2352-1791},
address = {Amsterdam [u.a.]},
publisher = {Elsevier},
reportid = {FZJ-2020-05100},
pages = {100878 -},
year = {2020},
abstract = {Fuel permeation and retention in fusion reactor wall
materials are important issues for plasma operation and
safety reasons in ITER. The austenitic stainless steel
316L(N)-IG will be used as structural material in the first
wall components in ITER. The impact of deuterium plasma
exposure on the deuterium permeation and retention was
studied. Polished 316L(N)-IG steel samples were deuterium
plasma exposed with an ion energy of 200 eV and at two
different fluences. Deuterium gas-driven permeation and
thermal desorption spectroscopy measurements were performed
afterwards. By comparison of the exposed samples to an
unexposed sample, it is concluded that the surface roughness
due to plasma exposure has no significant influence on the
deuterium permeation through the samples. The first results
of thermal desorption spectroscopy analysis show that the
main release of retained deuterium is between 600 and 900
and the release temperature increases by increasing the
plasma fluence.},
cin = {IEK-4},
ddc = {624},
cid = {I:(DE-Juel1)IEK-4-20101013},
pnm = {113 - Methods and Concepts for Material Development
(POF3-113)},
pid = {G:(DE-HGF)POF3-113},
typ = {PUB:(DE-HGF)16},
UT = {WOS:000600734700070},
doi = {10.1016/j.nme.2020.100878},
url = {https://juser.fz-juelich.de/record/888658},
}