Results 31 to 40 of about 66,536 (109)

Exploring the application of the parareal algorithm to edge simulations using the SOLPS-code [PDF]

, 2022
One of the most challenging obstacles to economically viable magnetically confined fusion power is how to deal with hot plasma when it inevitably interacts with solid surfaces.
Marin, Michele
core  

Comparison between MAST-U conventional and Super-X configurations through SOLPS-ITER modelling

, 2022
Input and output files for the simulations presented in the Nuclear Fusion paper "Comparison between MAST-U conventional and Super-X configurations through SOLPS-ITER ...
Fil, Alexandre
core   +1 more source

SOLPS-ITER simulations of a vapour box design for the linear device Magnum-PSI

, 2023
<p>Replication package for manuscript "SOLPS-ITER simulations of a vapour box design for the linear device Magnum-PSI" submitted to PPCF.</p ...
T W Morgan, J Gonzalez, E Westerhof
core   +1 more source

The new SOLPS-ITER code package

, 2014
The SOLPS-ITER package represents a renewed coupling of the up-to-date parallelized EIRENE Monte-Carlo code and the B2.5 edge plasma solver. Each part of the fluid-kinetic code system has been dismantled and analysed.
Dekeyser, W., Lisgo, Steve, Pitts, Richard, Wiesen, Sven, Baelmans, Martine, Baelmans, M., Voskoboynikov, Sergey, Kukushkin, A., Kukushkin, A. S., Kotov, Vladislav, Saibene, G., Kotov, V., Reiter, Detlev, Reiter, D., Pitts, R. A., Dekeyser, Wouter, Boerner, P., Kukushkin, Andre, Lisgo, S. W., Rozhansky, V., Veselova, I., Voskoboynikov, S., Rozhansky, Vladimir, Saibene, Gabriella, Wiesen, S.   +24 more
core   +1 more source

Finalizing the SOLPS-ITER vs. SOLPS4.3 benchmark for the ITER divertor

, 2021
Finalizing the SOLPS-ITER vs. SOLPS4.3 benchmark for the ITER divertorS. Wiesena, X. Bonninb, R. A. Pittsb, A. S. Kukushkinc,daForschungszentrum Jülich GmbH, Institut für Energie- und Klimaforschung - Plasmaphysik, D-52425 Jülich, GermanybITER ...
Pitts, R. A., Bonnin, X., Kukushkin, A. S., Wiesen, S.   +3 more
core  

SOLPS-ITER modeling of ASDEX Upgrade L-mode detachment states [PDF]

, 2021
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., Wischmeier M., Zanino R., Wu H., Subba F.   +4 more
core   +1 more source

Parameter optimization of the reduced-order scrape-off-layer model DIV1D using Markov-Chain Monte Carlo sampling

Nuclear Fusion
Accurate and efficient modeling of scrape-off layer (SOL) dynamics is essential for controlling divertor detachment in future fusion reactors. The reduced-order SOL model DIV1D provides a fast alternative to high-fidelity codes such as SOLPS-ITER, but it
R.R.M. Hazelhof, G.L. Derks, C.V. Verhoosel, S. Dasbach, D. vander Mijnsbrugge, S. Wiesen   +5 more
doaj   +1 more source

Global SOLPS-ITER and ERO2.0 coupling in linear devices: study plasma-wall interaction in helium plasma

, 2022
Helium (He) plasma is foreseen to characterize the Pre-Fusion Power Operation phase (PFPO) in ITER. Due to its peculiar effects on plasma-facing materials with respect to hydrogenic plasmas, plasma-wall interaction (PWI) in He must be carefully ...
Tonello E, Carminati P, Uccello A, Alberti G, Passoni M   +4 more
core  

Coupling Fluid Neutrals to Gyrokinetic Plasma Dynamics for Edge and SOL Turbulence Simulations

Contributions to Plasma Physics, EarlyView.
ABSTRACT Accurate modeling of turbulent transport in magnetic confinement fusion devices requires extending first‐principles gyrokinetic simulations from the core to the edge and scrape‐off layer (SOL), where additional physics—particularly plasma–neutrals interactions—must be included.
Sabine Ogier‐Collin, Philipp Ulbl, Wladimir Zholobenko, Frank Jenko   +3 more
wiley   +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