Results 1 to 10 of about 589 (158)

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.
Jeremy Mateja   +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.
Muyuan Li, Rudolf Neu, Martin 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

Physics basis for the first ITER tungsten divertor

open access: yesNuclear Materials and Energy, 2019
On the eve of component procurement, this paper discusses the present physics basis for the first ITER tungsten (W) divertor, beginning with a reminder of the key elements defining the overall design, and outlining relevant aspects of the Research Plan accompanying the new “staged approach” to ITER nuclear operations which fixes the overall divertor ...
Ilya Senichenkov   +2 more
exaly   +4 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.
Peter 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

Home - About - Disclaimer - Privacy