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@ARTICLE{Tokar:891393,
author = {Tokar, Mikhail},
title = {{A}n assessment of the first wall and limiter erosion
during limiter discharge stages in {DEMO}},
journal = {Nuclear fusion},
volume = {59},
number = {7},
issn = {1741-4326},
address = {Vienna},
publisher = {IAEA},
reportid = {FZJ-2021-01482},
pages = {076002 -},
year = {2019},
abstract = {The model elaborated on previously (Tokar 2018 Nucl. Fusion
58 016016) for the transport of neutral and charged plasma
components in the DEMO scrape-off layer (SOL) with a
divertor is reworked to describe limiter discharge phases.
It provides radial profiles of the plasma density and
temperatures of electrons and ions, averaged over flux
surfaces, which are calculated self-consistently at the edge
of the confined region and in the SOL, without prescribing
any decay lengths at the last closed flux surface. It is
assumed that on the limiter discharge phase in question the
plasma will be in the L-mode of the energy confinement and
the radial transport in the SOL is modeled with coefficients
of the Bohm type. Computations give the plasma particle
flows both to the limiters and to the first wall (FW). This
allows us to assess the erosion rates by plasma ions of
these reactor components. In the case of the FW physical
sputtering with hot atoms generated in charge-exchange
collisions of ions with neutral species, recycling from the
wall and limiters is also taken into account.},
cin = {IEK-4},
ddc = {620},
cid = {I:(DE-Juel1)IEK-4-20101013},
pnm = {174 - Plasma-Wall-Interaction (POF3-174)},
pid = {G:(DE-HGF)POF3-174},
typ = {PUB:(DE-HGF)16},
UT = {WOS:000468875900002},
doi = {10.1088/1741-4326/ab1434},
url = {https://juser.fz-juelich.de/record/891393},
}