Results 1 to 10 of about 261 (113)
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
I Senichenkov, E Kaveeva, V Rozhansky
exaly +3 more sources
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 Coster, V Rozhansky
exaly +2 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 ...
E Kaveeva, V Rozhansky, I Senichenkov
exaly +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
W Dekeyser, I Senichenkov, E Kaveeva
exaly +3 more sources
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 ...
S Wiesen, S Brezinsek, X Bonnin
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.
W Dekeyser, X Bonnin, S W Lisgo
exaly +3 more sources
SOLPS-ITER modification for impurity transport modelling in the tokamak pedestal region
Nuclear Materials and EnergyKinetic 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.
E Kaveeva, V Rozhansky, V Korzueva
exaly +3 more sources
Nuclear Materials and Energy, 2019 The SOLPS-ITER code suite is used worldwide for plasma edge modeling, the interpretation of experiments, as well as for the design of the ITER divertor. The numerical scheme of the plasma solver of the code, B2.5, is based on the assumption of perfectly ...
W Dekeyser, X Bonnin, Richard A Pitts
exaly +3 more sources
SOLPS-ITER simulations of the ITER divertor with improved plasma-facing component geometry
Nuclear Materials and EnergyThe ITER divertor design has been guided by SOLPS4.3 plasma boundary code simulations focused on baseline burning conditions at QDT = 10 which compose the majority of the existing ITER divertor scenario database.
R A Pitts
exaly +3 more sources
Parametric scaling of power exhaust in EU-DEMO alternative divertor simulations
Nuclear Materials and Energy, 2023 Investigations of parametric scaling of power exhaust in the alternative divertor configuration (ADC) SOLPS-ITER simulation database of the EU-DEMO are conducted and compared to predictions based on the Lengyel model.
A.E. Järvinen +5 more
doaj +1 more source