Results 91 to 100 of about 249 (122)
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SOLPS‐ITER EU‐DEMO modelling with drifts and kinetic neutrals

Contributions to Plasma Physics, 2022
AbstractThe edge transport modelling of EU‐DEMO burning plasma is performed by SOLPS‐ITER transport code with kinetic neutrals and full drifts and currents switched on. The efficiency of Ar and Ne as a divertor radiant is compared for such a condition. It is found from simulations that both Ar and Ne are suitable to reduce the target heat loads below ,
Vekshina E.   +7 more
openaire   +2 more sources

The new SOLPS-ITER code package

Journal of Nuclear Materials, 2015
Abstract 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. For SOLPS-ITER, full backwards compatibility with previous SOLPS4.3 ITER reference simulations is critical.
S. Wiesen   +11 more
openaire   +1 more source

Comparison of SOLPS5.0 and SOLPS‐ITER simulations for ASDEX upgrade L‐mode

Contributions to Plasma Physics, 2020
AbstractThis paper examines the backward compatibility of SOLPS‐ITER with SOLPS5.0 and produces a basic test of the physics/numerics improvements/additions in SOLPS‐ITER recommended by developers, taking an ASDEX Upgrade L‐mode simulation as an example. SOLPS‐ITER, which is emerging as the most advanced tool for edge plasma modelling, can be instructed
H. Wu   +3 more
openaire   +2 more sources

Predictive modeling of HL-2M divertor operation by SOLPS-ITER

Fusion Engineering and Design, 2018
Abstract HL-2M is a new medium-sized copper-conductor tokamak and is currently under construction. The SOLPS-ITER code package is applied to explore the operation range and the basic behaviors of the divertor plasma in the first phase. With scanning edge plasma densities, detailed modeling is carried out to study power load, electron and ion ...
Chengzhi Cao   +4 more
openaire   +1 more source

SOLPS-ITER modeling of CFETR advanced divertor with Ar and Ne seeding

Nuclear Fusion, 2022
Abstract The Chinese Fusion Engineering Testing Reactor (CFETR) is a project proposed by the Chinese fusion community to bridge the gap between ITER and a commercial fusion power plant with fusion power up to 1 GW. The mitigation of divertor target heat fluxes for such a powerful machine is a challenging problem, which might appear to be
I.Yu. Senichenkov   +12 more
openaire   +1 more source

Simulation of Liquid Lithium Divertor Geometry Using SOLPS-ITER

IEEE Transactions on Plasma Science, 2022
J. D. Lore   +6 more
openaire   +1 more source

Control of edge plasma by plate biasing in SOLPS‐ITER modeling

Contributions to Plasma Physics
AbstractThe effect of differential biasing of the divertor plates in a tokamak is analyzed using SOLPS‐ITER modeling with account of drifts and currents in the SOL. The ASDEX‐Upgrade like geometry and transport parameters adjusted for modeling of the semi‐detached nitrogen‐seeded plasma of shot #28903 are used in analysis.
V. A. Rozhansky   +2 more
openaire   +1 more source

A full and heterogeneous model of the ITER tokamak for comprehensive nuclear analyses

Nature Energy, 2021
Rafael Juarez   +2 more
exaly  

Simulation of EAST edge plasma using SOLPS-ITER/BOUT++ coupling

Nuclear Fusion, 2020
D.R. Zhang   +4 more
openaire   +1 more source

TRT Divertor Optimization in SOLPS-ITER Modeling

Plasma Physics Reports
P. A. Molchanov   +5 more
openaire   +1 more source

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