Results 1 to 10 of about 266 (114)

SOLPS-ITER modeling of Ar and N seeded discharges in ASDEX upgrade and ITER

Nuclear Materials and Energy, 2023
In this paper SOLPS-ITER simulations of Ar and N seeded discharges are presented for H-mode conditions on ASDEX Upgrade and for burning plasmas on ITER. These discharges are additionally compared with Ne seeded cases for both tokamaks. It is demonstrated
X Bonnin, R A Pitts
exaly   +3 more sources

Impact of the improved parallel kinetic coefficients on the helium and neon transport in SOLPS‐ITER for ITER

Contributions To Plasma Physics, 2022
Abstract New Grad–Zhdanov module is implemented in the SOLPS‐ITER code and applied to ITER impurity transport simulations. Significant difference appears in the helium transport due to improved parallel kinetic coefficients. As a result, 30% decrease of the separatrix‐averaged helium relative concentration is observed for the constant helium source and
S.O. Makarov, D.P. Coster, V.A. Rozhansky, S.P. Voskoboynikov, E.G. Kaveeva, I.Y. Senichenkov, A.A. Stepanenko, V.M. Zhdanov, X. Bonnin   +8 more
exaly   +2 more sources

SOLPS-ITER modeling of beryllium trace impurity in ITER [PDF]

MATEC Web of Conferences, 2018
Beryllium transport modeling was carried out in the trace impurity regime by SOLPS-ITER code for tokamak ITER. It is valuable for developing of diagnostics protection from beryllium deposition.
Makarov Sergei, Kaveeva Elizaveta
doaj   +2 more sources

Impact of drifts in the ASDEX upgrade upper open divertor using SOLPS‐ITER [PDF]

Contributions to Plasma Physics, Volume 60, Issue 5-6, June-July 2020., 2020
Abstract SOLPS‐ITER L‐mode‐like simulations with the full set of currents and drift velocities activated, and fluid neutrals have been carried out to interpret experimental results obtained in AUG. Drifts are critical to quantitatively reproduce the experimental results; however, simulations without drifts can also reproduce some trends qualitatively ...
I. Paradela Pérez, M. Groth, M. Wischmeier, D. Coster, D. Brida, P. David, D. Silvagni, M. Faitsch, the ASDEX‐Upgrade Team, the EUROfusion MST1 Team   +9 more
wiley   +4 more sources

SOLPS-ITER drift modelling of ITER burning plasmas with narrow near-SOL heat flux channels

Nuclear Materials and Energy, 2021
SOLPS-ITER code simulations with fluid drifts activated are used to examine the consequences for divertor performance, under burning plasma conditions, of a reduction in scrape-off layer (SOL) cross-field transport such that the outboard midplane SOL ...
Ilya Senichenkov, Richard Pitts, Bonnin X   +2 more
exaly   +3 more sources

Numerical error analysis of SOLPS-ITER simulations of EAST

Nuclear Fusion, 2022
Plasma edge simulations with codes like SOLPS-ITER are widely employed to interpret fusion experiments. However, numerical errors appearing in such simulations are rarely investigated, despite their potential large impact on simulation results.
Dieter Boeyaert, Stefano Carli, Kristel Ghoos, Wouter Dekeyser, Sven Wiesen, Martine Baelmans   +5 more
doaj   +3 more sources

Plasma edge simulations including realistic wall geometry with SOLPS-ITER

Nuclear Materials and Energy, 2021
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
Ilya Senichenkov, Elena Vekshina, Martine Baelmans   +2 more
exaly   +3 more sources

On the role of finite grid extent in SOLPS-ITER edge plasma simulations for JET H-mode discharges with metallic wall

Nuclear Materials and Energy, 2018
The impact of the finite grid size in SOLPS-ITER edge plasma simulations is assessed for JET H-mode discharges with a metal wall. For a semi-horizontal divertor configuration it is shown that the separatrix density is at least 30% higher when a narrow ...
Mathias Groth, Christophe Guillemaut, Marco Wischmeier   +2 more
exaly   +3 more sources

SOLPS-ITER Study of neutral leakage and drift effects on the alcator C-Mod divertor plasma

Nuclear Materials and Energy, 2017
As part of an effort to validate the edge plasma model in the SOLPS-ITER code suite under ITER-relevant divertor plasma and neutral conditions, we report on progress in the modeling of the Alcator C-Mod divertor plasma with the new code.
Wouter Dekeyser, Brian Labombard, Dan Brunner   +2 more
exaly   +3 more sources

SOLPS-ITER modification for impurity transport modelling in the tokamak pedestal region

Nuclear Materials and Energy
Kinetic corrections to SOLPS-ITER fluid equations are made to extend their applicability for description of the neoclassical part of impurity transport to collisionless regimes of the main ions.
Veronika Korzueva, Bonnin X, Kaveeva Elizaveta   +2 more
exaly   +3 more sources