Results 11 to 20 of about 585 (174)

Tungsten erosion and divertor leakage from the DIII-D SAS-VW tungsten-coated divertor in experiments with neon gas seeding

open access: yesNuclear Materials and Energy, 2023
Collector probes have been used to examine tungsten divertor leakage in a variety of scenarios with low-Z impurity seeding during operation with the new tungsten-coated SAS-VW divertor in DIII-D.
Matthew S Parsons   +2 more
exaly   +4 more sources

Experiences with a solid tungsten divertor in ASDEX Upgrade

open access: yesNuclear Materials and Energy, 2017
In 2013 a redesigned solid tungsten divertor, Div-III, was installed in ASDEX Upgrade. In two experimental campaigns more than 2700 plasma discharges with up to 10s duration, 110MJ plasma heating, and reaching a Psep/R of 10MW/m were conducted.
A Herrmann, I Zammuto, M Balden
exaly   +5 more sources

Liquid lithium as divertor material to mitigate severe damage of nearby components during plasma transients [PDF]

open access: yesScientific Reports, 2022
The successful operation of thermonuclear fusion reactors such as ITER, DEMO, and future commercial plants is mainly determined by the optimum choice of materials for various components.
V. Sizyuk, A. Hassanein
doaj   +2 more sources

Structural impact of creep in tungsten monoblock divertor target at 20 MW/m 2

open access: yesNuclear Materials and Energy, 2018
In order to increase erosion lifetime of the divertor target, in the 2nd design phase of R&D work package ‘Divertor’ for European DEMO, armor thickness of tungsten monoblock divertor target is increased from 5 mm to 8 mm.
Muyuan Li, Jeong-Ha You
exaly   +3 more sources

Extreme Ultraviolet Spectra of Few-Times Ionized Tungsten for Divertor Plasma Diagnostics

open access: yesAtoms, 2015
The extreme ultraviolet (EUV) emission from few-times ionized tungsten atoms has been experimentally studied at the Livermore electron beam ion trap facility.
Joel Clementson, P Beiersdorfer
exaly   +3 more sources

Validation of the plasma-wall interaction simulation code ERO2.0 by the analysis of tungsten migration in the open divertor region in the Large Helical Device

open access: yesNuclear Materials and Energy, 2022
Tungsten migration in the open divertor region in the Large Helical Device is analyzed for validating the three-dimensional plasma-wall interaction simulation code ERO2.0.
M. Shoji   +6 more
doaj   +1 more source

On the prediction and monitoring of tungsten prompt redeposition in tokamak divertors

open access: yesNuclear Materials and Energy, 2021
As net erosion of tungsten plasma-facing components in tokamak divertors is strongly reduced by tungsten prompt redeposition, predicting and monitoring tungsten prompt redeposition is crucial to estimate the lifetime of tungsten PFCs and the source of ...
J. Guterl, I. Bykov, R. Ding, P. Snyder
doaj   +1 more source

Modeling the effect of nitrogen recycling on the erosion and leakage of tungsten impurities from the SAS-VW divertor in DIII-D during nitrogen gas injection

open access: yesNuclear Materials and Energy, 2022
The new SAS-VW divertor in DIII-D has tungsten-coated components to enable the study of tungsten erosion and leakage from a closed, slot-like divertor. A proposed method of actively managing the tungsten impurities is to inject low-Z impurities, such as ...
Matthew S. Parsons   +2 more
doaj   +1 more source

Tungsten erosion and redeposition in the all-tungsten divertor of ASDEX Upgrade [PDF]

open access: yesPhysica Scripta, 2009
Net erosion and deposition of tungsten (W) in the ASDEX Upgrade divertor were determined after the 2007 campaign by using thin W marker stripes. ASDEX Upgrade had full-W plasma-facing components during this campaign. The inner divertor and the roof baffle were net W deposition areas with a maximum deposition of about 1×1018 W-atoms cm-2 in the private ...
Mayer, M.   +17 more
openaire   +3 more sources

Investigation of the impact of flux expansion on tungsten content and radiation in JET-ILW

open access: yesNuclear Materials and Energy, 2021
The present paper shows the results of the investigation about the effects of the flux-expansion variation at the inner strike point location on the tungsten content in the plasma core, and on the bulk radiation in JET-ILW.
S. Minucci   +6 more
doaj   +1 more source

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