Results 31 to 40 of about 249 (122)

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, R.A. Pitts, Dan Brunner, Brian LaBombard, Jim L. Terry   +6 more
doaj   +1 more source

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 ...
S. Wiesen, S. Brezinsek, X. Bonnin, E. Delabie, L. Frassinetti, M. Groth, C. Guillemaut, J. Harrison, D. Harting, S. Henderson, A. Huber, U. Kruezi, R.A. Pitts, M. Wischmeier   +13 more
doaj   +1 more source

Interchange‐turbulence‐based radial transport model for SOLPS‐ITER: A COMPASS case study [PDF]

Contributions to Plasma Physics, 2020
AbstractMean‐field plasma edge transport codes such as SOLPS‐ITER heavily rely on ad‐hoc radial diffusion coefficients to approximately model anomalous transport. Such coefficients are experimentally determined and vary between different machines, and also depend on the operational regime and plasma location within the same device.
Carli, Stefano, Dekeyser, Wouter, Coosemans, Reinart, Dejarnac, Renaud, Komm, Michael, Dimitrova, Miglena, Adamek, Jiri, Bilkova, Petra, Bohm, Petr   +8 more
openaire   +1 more source

Comparison between SOLPS-ITER and B2.5-Eunomia for simulating Magnum-PSI

Plasma Physics and Controlled Fusion, 2022
Abstract The interaction between plasma, neutrals and surfaces in fusion reactors is of immense importance for heat and particle control, especially for the next generation of devices. Heat loads of 10 MW
Gonzalez, J., Chandra, R., de Blank, H. J., Westerhof, E.   +4 more
openaire   +3 more sources

SOLPS-ITER modeling of deuterium throughput impact on the ITER SOL plasma

Nuclear Materials and Energy, 2023
The impact of the ionization source in the ITER far SOL associated with main chamber deuterium puffing on the overall SOL performance is studied numerically using SOLPS-ITER modeling. It is found out that this source can have significant influence on the
E. Kaveeva, S. Makarov, I. Senichenkov, V. Rozhansky, I. Veselova, X. Bonnin, R.A. Pitts   +6 more
doaj   +1 more source

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.
V. Korzueva, E. Kaveeva, V. Rozhansky, X. Bonnin   +3 more
doaj   +1 more source

Stabilization of EMC3-EIRENE for detachment conditions and comparison to SOLPS-ITER

Nuclear Materials and Energy, 2019
Numerical access to cold divertor conditions in tokamaks with EMC3-EIRENE has been proven to be challenging, but is now possible for the first time after a linearization of the electron energy sink term from interaction with neutral gas.
H. Frerichs, X. Bonnin, Y. Feng, A. Loarte, R.A. Pitts, D. Reiter, O. Schmitz   +6 more
doaj   +1 more source

Comparing N versus Ne as divertor radiators in ASDEX-upgrade and ITER

Nuclear Materials and Energy, 2019
The study aims to estimate the influence of machine scale size on the behavior of plasma with extrinsic seeded impurities in the scrape-off layer (SOL) and divertor.
Elizaveta Sytova, Richard A. Pitts, Elizaveta Kaveeva, Xavier Bonnin, David Coster, Vladimir Rozhansky, Ilya Senichenkov, Irina Veselova, Sergey Voskoboynikov, Felix Reimold   +9 more
doaj   +1 more source

Modeling of tungsten impurity transport and distribution in EAST based on multi-fluid and kinetic Monte Carlo simulations

AIP Advances
In recent years, the materials of plasma facing components, such as divertor target plates, domes, and outer walls of tokamaks, such as ASDEX Upgrade, WEST, JET, EAST, and ITER, have been changed from carbon to tungsten because of its lower erosion and ...
Ziyang Wen, YiPing Chen, Ling Zhang
doaj   +1 more source

Predictive SOLPS-ITER simulations to study the role of divertor magnetic geometry in detachment control in the MAST-U Super-X configuration

Nuclear Fusion, 2023
The SOLPS-ITER code has been utilised to study the movement of the detachment front location from target towards the X-point for MAST-U Super-X plasmas.
O. Myatra, B. Lipschultz, D. Moulton, K. Verhaegh, B. Dudson, S. Orchard, A. Fil, C. Cowley   +7 more
doaj   +1 more source