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@PHDTHESIS{Koza:37539,
author = {Koza, Yoshie},
title = {{P}erformance of {M}etallic and {C}arbon-{B}ased
{M}aterials {U}nder the {I}nfluence of {I}ntense {T}ransient
{E}nergy {D}eposition},
volume = {4137},
issn = {0944-2952},
school = {Techn. Hochsch. Aachen},
type = {Dr. (FH)},
address = {Jülich},
publisher = {Forschungszentrum Jülich GmbH Zentralbibliothek, Verlag},
reportid = {PreJuSER-37539, Juel-4137},
series = {Berichte des Forschungszentrums Jülich},
pages = {II, 140 S.},
year = {2004},
note = {Record converted from VDB: 12.11.2012; Aachen, Techn.
Hochsch., Diss., 2004},
abstract = {Intense energy is deposited on localized areas of the
plasma facing materials under transient thermal loads such
as edge localized modes (ELMS), plasma disruptions or
vertical displacement events (VDEs) in a magnetic confined
fusion reactor. Crack formation, thermal erosion and
redeposition mainly take place under these conditions and
may cause catastrophic damage in the materials. Dust
formation associated with evaporation and liquid or solid
particles emission are also serious issues to influence
plasma contamination. In order to estimate the lifetime of
the components during above mentioned events (ELMS,
disruptions, VDEs), the thermal erosion mechanisms and
performance of carbon-based and high Z materials have been
investigated using energetic electron beam facilities.
Moreover, a thorough calibration of an electron beam in the
high heat flux facility JUDITH was done. For the evaluation
of erosion data obtained in different test facilities
several factors have to be taken into account. Different
material erosion processes at identical heat loads induced
by different facilities take place due to different beam
generation and beam modes (static/scanned beam). The
different degradation processes were created by different
surface tensions and vapor recoil pressures at local spots
in the loaded area. Molten and re-solidified material
remained within the loaded area by fast scanning of the
electron beam in JUDITH, which leaded to a rippling surface.
Erosion scenarios have been elucidated on pure W and
carbon-based materials. For W, the thermal erosion is
initiated by convection of melt, strong evaporation or
boiling processes. Moreover the formation of a vapor cloud
was observed in the simulation experiments indicating vapor
shielding on the surface. From screening tests on different
high Z materials, pure Wwas found to show the highest
resistance against thermal shock under plasma disruption
conditions and are suitable for the components in Tokamak
fusion reactors. A castellated structure was found to help
reducing crack formation compared to monolithic structure.
For carbon-based materials (isotropic graphite,
$\underline{c}$arbon $\underline{f}$iber
$\underline{c}$omposites (CFCs), Si-doped CFC), material
erosion in different particle emission regimes, and
characterization of emitted particles have been studied.
"Small" and "Big" particle emission regimes have been
identified under brittle destruction, which represents the
combined action of sublimation, crack formation and ejection
of solid particles. These regimes were related to the
ejected particle size and maximum erosion depth. The
resulting erosion patterns on the test samples and the
morphology of the ejected particles differ significantly for
the three materials. For both carbon and tungsten,
preheating of samples before loading enhances material
damages such as weight loss and crater formation.},
cin = {IWV-2},
cid = {I:(DE-Juel1)VDB2},
pnm = {Kernfusion und Plasmaforschung},
pid = {G:(DE-Juel1)FUEK250},
typ = {PUB:(DE-HGF)11 / PUB:(DE-HGF)3},
url = {https://juser.fz-juelich.de/record/37539},
}