Results 81 to 90 of about 311,592 (233)

ERO and PIC simulations of gross and net erosion of tungsten in the outer strike-point region of ASDEX Upgrade

open access: yesNuclear Materials and Energy, 2017
We have modelled net and gross erosion of W in low-density l-mode plasmas in the low-field side strike point region of ASDEX Upgrade by ERO and Particle-in-Cell (PIC) simulations.
A. Hakola   +9 more
doaj   +1 more source

Recent progress in modeling ICRF-edge plasma interactions with application to ASDEX Upgrade

open access: yesNuclear Fusion, 2021
This paper summarizes recent progress in modeling the interaction between ion cyclotron range of frequency (ICRF) waves and edge plasma with application to ASDEX Upgrade.
W. Zhang   +13 more
semanticscholar   +1 more source

X-point radiator control and its dynamics in ASDEX Upgrade and JET deuterium–tritium discharges

open access: yesNuclear Fusion
Control of heat exhaust is essential for the operation of power producing fusion reactors. Here, we present results of heat exhaust feedback control experiments in JET and AUG.
T. Bosman   +23 more
semanticscholar   +1 more source

Validation of the Fenix ASDEX Upgrade flight simulator

open access: yes, 2021
Fenix [1] , [2] is the ASDEX Upgrade (AUG) flight simulator based on the 1-D transport code ASTRA coupled with the 2-D equilibrium solver [ 3 ] SPIDER and Simulink (simulation platform integrated with MATLAB).
F. Janky   +9 more
semanticscholar   +1 more source

Overview of the EUROfusion Tokamak Exploitation programme in support of ITER and DEMO

open access: yesNuclear Fusion
Within the 9th European Framework programme, since 2021 EUROfusion is operating five tokamaks under the auspices of a single Task Force called ‘Tokamak Exploitation’.
E. Joffrin   +814 more
doaj   +1 more source

Validation of a full-plasma integrated modeling approach on ASDEX Upgrade

open access: yesNuclear Fusion, 2021
In this work we present the extensive validation of a refined version of the integrated model based on engineering parameters (IMEP) introduced in reference (Luda et al 2020 Nucl. Fusion 60 036023).
T. Luda   +11 more
semanticscholar   +1 more source

Modelling of carbon transport in the outer divertor plasma of ASDEX upgrade

open access: yes, 2009
Carbon transport in the ASDEX Upgrade outer divertor plasma is investigated in numerical simulations. The SOLPS5.0 code package is used to model the scrape-off layer plasma in a set of repeated lower-single-null L-mode discharges.
Wischmeier, M.   +33 more
core   +1 more source

Reduced models for the maximum vertical force in a tokamak device

open access: yesNuclear Fusion
A formula was suggested in Miyamoto et al (2011 Plasma Phys. Control. Fusion 53 082001) to calculate the total maximum vertical force due to a vertical displacement event in a tokamak device without modeling the whole phenomenon.
G. Pautasso   +2 more
doaj   +1 more source

A study on the density shoulder formation in the SOL of H-mode plasmas

open access: yesNuclear Materials and Energy, 2017
The term “shoulder formation” refers to an increase of the density decay length in the scrape-off layer (SOL) observed in many tokamaks during L-mode operation when a density threshold is reached.
D. Carralero   +11 more
doaj   +1 more source

Carbon erosion and a:C-H layer formation at ASDEX Upgrade

open access: yes, 2005
During the campaign 2002–2003 a carbon erosion and deposition experiment was performed in the lower divertor of ASDEX Upgrade. A complete divertor cross section with erosion sensitive markers, deposition monitors below the divertor and time resolved ...
Vainonen-Ahlgren, E.   +8 more
core   +1 more source

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