Results 71 to 80 of about 585 (174)

The impacts of lithium and silicon coating on the W source in EAST

open access: yesNuclear Materials and Energy, 2017
Application of lithium (Li) or silicon (Si) wall coating in the Experimental Advanced Superconducting Tokamak (EAST) has proven to be an effective method to reduce fuel recycling and control impurity level, and also to improve the plasma performance.
Hongmin Mao   +17 more
doaj   +1 more source

WEST full tungsten operation with an ITER grade divertor

open access: yesNuclear Fusion
The mission of WEST (tungsten-W Environment in Steady-state Tokamak) is to explore long pulse operation in a full tungsten (W) environment for preparing next-step fusion devices (ITER and DEMO) with a focus on testing the ITER actively cooled W divertor ...
J. Bucalossi   +390 more
doaj   +1 more source

Hydrogen inventory simulations for PFCs (HISP)

open access: yesNuclear Materials and Energy
Hydrogen Inventory Simulations for Plasma facing components (HISP) is an open-source simulation tool to model the evolution of hydrogen (H) isotopes inventory in plasma-facing-components (PFCs) of magnetic confinement fusion devices. The objective was to
Kaelyn Dunnell   +5 more
doaj   +1 more source

Experimental validation of a model for particle recycling and tungsten erosion during ELMs in the DIII-D divertor

open access: yesNuclear Materials and Energy, 2018
A refined version of the Fundamenksi-Moulton 'free-streaming' model (FSM) for the dynamics of divertor density, particle flux, and heat flux during edge localized modes (ELMs) is presented.
T. Abrams   +10 more
doaj   +1 more source

Global tungsten erosion and migration modeling for the EU-DEMO with the ERO2.0 code

open access: yesNuclear Fusion
Global tungsten migration, thus erosion, transport, and deposition, in the EU-DEMO tokamak is investigated using ERO2.0 simulations for an argon-seeded ELM-free H-mode plasma scenario with expected 2 GW fusion power developed with the narrow-grid version
C. Baumann   +7 more
doaj   +1 more source

Modelling fuel retention in the W divertor during the D/H/D changeover experiment in WEST

open access: yesNuclear Materials and Energy
A fuelling changeover experiment from Deuterium (D) to Hydrogen (H), and back has been performed in WEST to study the retention and removal in metallic devices with actively cooled ITER-grade tungsten divertor.
E.A. Hodille   +20 more
doaj   +1 more source

Multiscale numerical study of the ELM-induced sputtering on the tungsten castellated divertor gap

open access: yesNuclear Fusion
Material sputtering and erosion are key issue in fusion science. In the steady state, tungsten sputtering can be maintained at a low level. However, tungsten is seriously sputtered by the hot plasma from edge localized mode (ELM) bursts.
Guo-jian Niu   +8 more
doaj   +1 more source

Molecular dynamics simulation of tungsten surface sputtering under low–energy neon irradiation for radiative divertor scenarios

open access: yesNuclear Materials and Energy
Neon (Ne) is a key candidate impurity for radiative divertor operation in tokamaks, aiming to reduce the thermal load on the divertor targets. However, its injection can simultaneously enhance tungsten surface erosion.
Xianglong Liu   +9 more
doaj   +1 more source

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