% IMPORTANT: The following is UTF-8 encoded. This means that in the presence
% of non-ASCII characters, it will not work with BibTeX 0.99 or older.
% Instead, you should use an up-to-date BibTeX implementation like “bibtex8” or
% “biber”.
@ARTICLE{Dekeyser:904042,
author = {Dekeyser, W. and Boerner, P. and Voskoboynikov, S. and
Rozhanksy, V. A. and Senichenkov, I. and Kaveeva, L. and
Veselova, I. and Vekshina, E. and Bonnin, X. and Pitts, R.
A. and Baelmans, M.},
title = {{P}lasma edge simulations including realistic wall geometry
with {SOLPS}-{ITER}},
journal = {Nuclear materials and energy},
volume = {27},
issn = {2352-1791},
address = {Amsterdam [u.a.]},
publisher = {Elsevier},
reportid = {FZJ-2021-05612},
pages = {100999 -},
year = {2021},
abstract = {In plasma edge simulations using the SOLPS-ITER code, the
simulated Scrape-Off Layer plasma domain has historically
been restricted to magnetic flux surfaces contacting
divertor targets at both ends. We present here a newly
developed numerical solver for the B2.5 plasma solver in
SOLPS-ITER, allowing the numerical grid to be extended to
the true vessel boundaries. The new, unstructured Finite
Volume scheme can deal with arbitrary grids and magnetic
topologies in the 2D poloidal plane. It includes a correct
numerical treatment of possibly misaligned faces and cells
w.r.t. the magnetic field to cope with, for example, strong
divertor target shaping. The solver combines the benefits of
an accurate numerical separation of fast parallel and slow
radial transport, with a realistic description of the wall
geometry, and the possibility of local grid refinement to
capture sharp features in the Scrape-Off Layer flows.
Generalized sheath boundary conditions are presented that
can be imposed at all vessel boundaries, removing an
important modeling uncertainty related to the specification
of ad hoc decay length boundary conditions at the outer flux
surfaces. The resulting model is applied to an AUG
single-null case, a standard benchmark case for SOLPS-ITER.
We analyze in particular the impact of the extended plasma
model on upstream and divertor plasma conditions, and the
improved predictions of heat and particle loads to the main
chamber wall. The extended solver also allows for a much
improved qualitative agreement between fluid and kinetic
neutral simulations, because the fluid neutral solution,
which is obtained on the plasma grid, now also extends to
the true main chamber and divertor vessel boundaries.},
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:000670923000005},
doi = {10.1016/j.nme.2021.100999},
url = {https://juser.fz-juelich.de/record/904042},
}