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@ARTICLE{Borodin:891433,
author = {Borodin, D. and Romazanov, J. and Pitts, R. A. and Lisgo,
S. W. and Brezinsek, S. and Borodkina, I. and Eksaeva, Alina
and Safi, E. and Nordlund, K. and Kirschner, A. and
Linsmeier, Ch.},
title = {{I}mproved {ERO} modelling of beryllium erosion at {ITER}
upper first wall panel using {JET}-{ILW} and {PISCES}-{B}
experience},
journal = {Nuclear materials and energy},
volume = {19},
issn = {2352-1791},
address = {Amsterdam [u.a.]},
publisher = {Elsevier},
reportid = {FZJ-2021-01518},
pages = {510 - 515},
year = {2019},
abstract = {ERO is a 3D Monte-Carlo impurity transport and
plasma-surface interaction code. In 2011 it was applied for
the ITER first wall (FW) life time predictions [1] (critical
blanket module BM11). After that the same code was
significantly improved during its application to existing
fusion-relevant plasma devices: the tokamak JET equipped
with an ITER-like wall and linear plasma device PISCES-B.
This has allowed testing the sputtering data for beryllium
(Be) and showing that the “ERO-min” fit based on the
large $(50\%)$ deuterium (D) surface content is well
suitable for plasma-wetted areas (D plasma). The improved
procedure for calculating of the effective sputtering yields
for each location along the plasma-facing surface using the
recently developed semi-analytical sheath approach was
validated. The re-evaluation of the effective yields for
BM11 following the similar revisit of the JET data has
indicated significant increase of erosion and motivated the
current re-visit of ERO simulations.},
cin = {IEK-4},
ddc = {624},
cid = {I:(DE-Juel1)IEK-4-20101013},
pnm = {134 - Plasma-Wand-Wechselwirkung (POF4-134)},
pid = {G:(DE-HGF)POF4-134},
typ = {PUB:(DE-HGF)16},
UT = {WOS:000470746100080},
doi = {10.1016/j.nme.2019.03.016},
url = {https://juser.fz-juelich.de/record/891433},
}