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 ...
Sebastijan Brezinsek +2 more
exaly +5 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
Wouter Dekeyser +2 more
exaly +6 more sources
Drifts, currents, and power scrape-off width in SOLPS-ITER modeling of DIII-D [PDF]
The effects of drifts and associated flows and currents on the width of the parallel heat flux channel (λq) in the tokamak scrape-off layer (SOL) are analyzed using the SOLPS-ITER 2D fluid transport code.
Eric Meier +2 more
exaly +6 more sources
Parametric scaling of power exhaust in EU-DEMO alternative divertor simulations [PDF]
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 +5 more sources
SOLPS-ITER modeling of ASDEX Upgrade L-mode detachment states [PDF]
SOLPS-ITER is used to model ASDEX Upgrade L-mode detachment states including the onset of detachment, the fluctuating detachment, and the complete detachment states, considering drifts and mimicking filamentary convective transport with a radial outward ...
Cavedon, M. +4 more
core +8 more sources
SOLPS-ITER validation with TCV L-mode discharges editors-pick [PDF]
This work presents a quantitative test of SOLPS-ITER simulations against tokamak a configuration variable (TCV) L-mode experiments. These simulations account for drifts, currents, kinetic neutrals, and carbon impurities providing the most complete edge ...
Bagnato, F. +16 more
core +4 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 ...
Elizaveta Kaveeva +2 more
exaly +3 more sources
SOLPS-ITER modeling of beryllium trace impurity in ITER [PDF]
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]
AbstractSOLPS‐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 ...
Paradela Pérez, I. +9 more
openaire +3 more sources
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
I Y Senichenkov, Kaveeva Elizaveta
exaly +3 more sources

