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@ARTICLE{Spilker:808663,
author = {Spilker, Benjamin and Linke, Jochen and Pintsuk, Gerald and
Wirtz, Marius},
title = {{E}xperimental {S}tudy of {ELM}-{L}ike {H}eat {L}oading on
{B}eryllium under {ITER} {O}perational {C}onditions},
journal = {Physica scripta},
volume = {T167},
issn = {0031-8949},
address = {Bristol},
publisher = {IoP Publ.},
reportid = {FZJ-2016-02296},
pages = {014024},
year = {2016},
abstract = {The experimental fusion reactor ITER, currently under
construction in Cadarache, France, is transferring the
nuclear fusion research to the power plant scale. ITER's
first wall (FW), armoured by beryllium, is subjected to high
steady state and transient power loads. Transient events
like edge localized modes not only deposit power densities
of up to 1.0 GW m−2 for 0.2–0.5 ms in the divertor of
the machine, but also affect the FW to a considerable
extent. Therefore, a detailed study was performed, in which
transient power loads with absorbed power densities of up to
1.0 GW m−2 were applied by the electron beam facility
JUDITH 1 on beryllium specimens at base temperatures of up
to 300 °C. The induced damage was evaluated by means of
scanning electron microscopy and laser profilometry. As a
result, the observed damage was highly dependent on the base
temperatures and absorbed power densities. In addition, five
different classes of damage, ranging from 'no damage' to
'crack network plus melting', were defined and used to
locate the damage, cracking, and melting thresholds within
the tested parameter space.},
cin = {IEK-2 / IEK-4},
ddc = {530},
cid = {I:(DE-Juel1)IEK-2-20101013 / I:(DE-Juel1)IEK-4-20101013},
pnm = {174 - Plasma-Wall-Interaction (POF3-174) / HITEC -
Helmholtz Interdisciplinary Doctoral Training in Energy and
Climate Research (HITEC) (HITEC-20170406)},
pid = {G:(DE-HGF)POF3-174 / G:(DE-Juel1)HITEC-20170406},
typ = {PUB:(DE-HGF)16},
UT = {WOS:000383504700025},
doi = {10.1088/0031-8949/T167/1/014024},
url = {https://juser.fz-juelich.de/record/808663},
}