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@INPROCEEDINGS{Unterberg:891688,
author = {Unterberg, B. and Zlobinski, Miroslaw and De Temmerman, G.
and Porosnicu, C. and Matveev, D. and Sergienko, G. and
Brezinsek, S. and Nicolai, D. and Rasinski, M. and Spilker,
B. and Freisinger, M. and Möller, S. and Linsmeier, Ch. and
Lungu, C. P. and Dinca, P.},
title = {{S}tability of deuterated beryllium layers on tungsten
substrates during transient heat loads by laser irradiation},
reportid = {FZJ-2021-01671},
year = {2021},
abstract = {24th Int. Conf. on Plasma Surface Interaction in Fusion
Devices (PSI-24) in Jeju, Korea, May 31st to June 5th, 2020
Stability of deuterated beryllium layers on tungsten
substrates during transient heat loads by laser
irradiationB. Unterberga, M. Zlobinskia,*, G. De Temmermanb,
C. Porosnicuc, D. Matveeva, G. Sergienkoa, S. Brezinseka, D.
Nicolaia, M. Rasinskia, B. Spilkera, M. Freisingera, S.
Möllera, Ch. Linsmeiera, C. P. Lunguc, P. Dincac aInstitute
of Energy and Climate Research – Plasma Physics,
Forschungszentrum Jülich GmbH (FZJ), Partner in the
Trilateral Euregio Cluster, D-52425 Jülich, GermanybITER
Organization, Route de Vinon-sur-Verdon, CS 90 046, 13067 St
Paul Lez Durance Cedex, FrancecNational Institute for Laser,
Plasma and Radiation Physics (INFLPR), Atomistilor 409,
Magurele, Jud Ilfov, 077125, Bucharest,
Romaniab.unterberg@fz-juelich.deA major contribution to
long-term hydrogen retention in ITER is expected in Be
layers on W divertor components [1]. Therefore, for ITER an
in-situ and spatially resolved diagnostic of in-vessel
retention has been qualified based on laser induced
desorption (LID) of tritium out of Be co-deposits [2]. In
this context, the stability of such layers is important in
view of possible dust production and flaking.Homogeneous Be
layers with different deuterium content (0.01-0.3 D/Be) and
layer thicknesses (1-20 μm) were deposited on W substrates
by HiPIMS (High Power Impulse Magnetron Sputtering) [3]. The
laser irradiation parameters have been varied between 0.5
and 5.0 MJ/m2 (diameter of the laser beam at the sample of 3
mm) with pulse lengths between 1 and 20 ms. Such loading
parameters also cover the power load densities during ELMs
in ITER. The surface temperature was monitored by a
pyrometer and ranged between 900 and 2300 K.Overall, the
stability of the Be layer is mostly governed by the
operational conditions during the coating process within the
magnetron. Best adhesion has been obtained for a surface
roughness of 150 nm of the substrate, chemical surface
cleaning and in-situ cleaning via GDC, and layer deposition
at a rate of 0.2 nm/s. These layers withstand the strongest
laser pulses even above melting onset without significant
detachment of layer fragments. Crack networks can be
observed below melting which are connected to tension during
the cool-down phase of the layer. When the deposition was
performed on less rough substrates (10-15 nm) with DC
deposition either the layer is fragmented in microscopic
parts, which are delaminated to a large extent, or even
complete macroscopic lamination is observed with a clear
separation into mm-sized delaminated areas with no remaining
layer fragments and remaining layer. SEM pictures show
hill-like structures on the μm scale with local
delamination surrounded by cracks. The different damage
categories can also be distinguished via the temperature
increase during the laser pulse: for macroscopic
delamination the pyrometer shows a steep temperature
increase until delamination, for microscopic delamination
the temperature still increases fasterthan on the best, most
adhesive layer, governed by the heat contact between layer
and substrateas described for plasma deposited carbon layers
in [4]. [1] S. Brezinsek, et al., Nucl. Fusion 55, 063021
(2015)[2] M. Zlobinski et al., Nuclear Materials and Energy,
Volume 19, May 2019, Pages 503-509[3] P. Dinca, et al.,
Surface $\&$ Coatings Tech. 321 (2017) 397-402[4] A.
Herrmann, Phys. Scr. T128 (2007) 234–238},
month = {Jan},
date = {2021-01-25},
organization = {24th International Conference on
Plasma Surface Interactions in
Controlled Fusion Devices (PSI 2020),
virtuell (virtuell), 25 Jan 2021 - 29
Jan 2021},
cin = {IEK-4 / IEK-1},
cid = {I:(DE-Juel1)IEK-4-20101013 / I:(DE-Juel1)IEK-1-20101013},
pnm = {134 - Plasma-Wand-Wechselwirkung (POF4-134)},
pid = {G:(DE-HGF)POF4-134},
typ = {PUB:(DE-HGF)1},
url = {https://juser.fz-juelich.de/record/891688},
}