Results 91 to 100 of about 249 (122)
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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
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The new SOLPS-ITER code package
Journal of Nuclear Materials, 2015Abstract 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
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Comparison of SOLPS5.0 and SOLPS‐ITER simulations for ASDEX upgrade L‐mode
Contributions to Plasma Physics, 2020AbstractThis 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
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Predictive modeling of HL-2M divertor operation by SOLPS-ITER
Fusion Engineering and Design, 2018Abstract 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
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SOLPS-ITER modeling of CFETR advanced divertor with Ar and Ne seeding
Nuclear Fusion, 2022Abstract 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
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Simulation of Liquid Lithium Divertor Geometry Using SOLPS-ITER
IEEE Transactions on Plasma Science, 2022J. D. Lore +6 more
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Control of edge plasma by plate biasing in SOLPS‐ITER modeling
Contributions to Plasma PhysicsAbstractThe 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
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A full and heterogeneous model of the ITER tokamak for comprehensive nuclear analyses
Nature Energy, 2021Rafael Juarez +2 more
exaly
Simulation of EAST edge plasma using SOLPS-ITER/BOUT++ coupling
Nuclear Fusion, 2020D.R. Zhang +4 more
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TRT Divertor Optimization in SOLPS-ITER Modeling
Plasma Physics ReportsP. A. Molchanov +5 more
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