Results 1 to 10 of about 66,536 (109)
SOLPS-ITER modeling of Ar and N seeded discharges in ASDEX upgrade and ITER
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
David Coster +2 more
exaly +4 more sources
SOLPS-ITER modification for impurity transport modelling in the tokamak pedestal region
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 +2 more
exaly +4 more sources
On the role of finite grid extent in SOLPS-ITER edge plasma simulations for JET H-mode discharges with metallic wall [PDF]
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 +2 more
exaly +4 more sources
SOLPS-ITER Study of neutral leakage and drift effects on the alcator C-Mod divertor plasma
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.
Xavier Bonnin +2 more
exaly +4 more sources
SOLPS-ITER simulations of the ITER divertor with improved plasma-facing component geometry
The 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, A A Pshenov
exaly +4 more sources
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
Xavier Bonnin, D P Coster
exaly +2 more sources
SOLPS-ITER drift modelling of ITER burning plasmas with narrow near-SOL heat flux channels
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 +2 more
exaly +3 more sources
Plasma edge simulations including realistic wall geometry with SOLPS-ITER
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 +2 more
exaly +3 more sources
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 ...
Richard Pitts +2 more
exaly +3 more sources
Parametric scaling of power exhaust in EU-DEMO alternative divertor simulations
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

