Results 91 to 100 of about 984 (168)

Integrated modeling of boron powder injection for real-time plasma-facing component conditioning

open access: yesNuclear Materials and Energy
An integrated modeling framework for investigating the application of solid boron (B) powder injection for real-time surface conditioning of plasma-facing components (PFCs) in tokamak environments is presented.
F. Effenberg   +8 more
doaj   +1 more source

Integrated simulation of the impacts of resonant magnetic perturbations on tungsten radiation on EAST

open access: yesNuclear Fusion
A significant reduction of 70% in tungsten (W) radiation intensity has been experimentally observed under resonant magnetic perturbation (RMP) fields on the EAST tokamak.
Z.H. Gao   +9 more
doaj   +1 more source

Heat flux mitigation characteristics in the radiative divertors with multi-peaks of heat flux in the large helical device [PDF]

open access: yes
ORCID 0000-0001-6090-5010In this study, the effects of impurity seeding on the one- and two-dimensional heat flux profiles of the large helical device divertor with a multi-peaks of heat flux were investigated, focusing on the heat-flux-reduction ...
123133   +13 more
core   +1 more source

Refined guiding centre approximation for kinetic studies of Nitrogen seeding in medium density ITER L-mode scenarios with EMC3-EIRENE

open access: gold, 2022
D. Harting   +7 more
openalex   +1 more source

Off-target gradient-driven flows in 3D simulations of ADITYA-Upgrade tokamak scrape-off layer plasma transport

open access: yesNuclear Fusion
Coupled plasma-neutral transport simulations are performed on ADITYA-Upgrade tokamak scrape-off layer (SOL) plasma, where flows in the core and SOL were measured to reverse signs with density variation.
Arzoo Malwal   +3 more
doaj   +1 more source

FLARE: field line analysis and reconstruction for 3D boundary plasma modeling

open access: yesNuclear Fusion
The FLARE code is a magnetic mesh generator that is integrated within a suite of tools for the analysis of the magnetic geometry in toroidal fusion devices.
H. Frerichs
doaj   +1 more source

Investigation of heat flux deposition on divertor target on the Large Helical Device with EMC3-EIRENE modelling

open access: green, 2017
Shuyu Dai   +8 more
openalex   +2 more sources

Divertor detachment in the pre-fusion power operation phase in ITER during application of resonant magnetic perturbations [PDF]

open access: yes, 2021
Bonnin, X.   +8 more
core   +1 more source

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