Results 31 to 40 of about 96,750 (196)

Model validation of tungsten erosion and redeposition properties using biased tungsten samples on DiMES

open access: yesNuclear Materials and Energy, 2023
An experiment was performed in the DIII-D lower divertor to validate numerical SOL tungsten (W) impurity erosion and redeposition simulations against experimental data. The net and gross erosion of W were calculated as a function of the voltage (or bias)
L. Cappelli   +14 more
doaj   +1 more source

Final Steps to an All Tungsten Divertor Tokamak [PDF]

open access: yesJournal of Nuclear Materials, 2007
Currently 85% of the plasma facing components of ASDEX Upgrade are tungsten coated. Carbon inux from W PFCs is still observed but a reduction of the C content is found in plasma discharges and a lower C fraction is measured in deposited layers in agreement with modelling.
Neu, R.   +16 more
openaire   +4 more sources

Direct Tungsten/Copper Bonding for Divertor Application

open access: yesPlasma and Fusion Research, 2022
We carried out a fundamental investigation of a uniaxial direct W-to-Cu bonding at relatively low temperatures in ambient air, which would potentially allow for simple preparation and maintenance of divertor wall components. W/Cu bonds formed at 500◦C with a bonding pressure of 0.1 MPa, but the mechanical interfacial strength was about 1 MPa ...
YAMAUCHI, Keisuke   +2 more
openaire   +1 more source

Tungsten spectroscopy relevant to the diagnostics of ITER divertor plasmas [PDF]

open access: yes, 2009
The possibility of using extreme ultraviolet emission from low charge states of tungsten ions to diagnose the divertor plasmas of the ITER tokamak has been investigated.
Beiersdorfer, P.   +14 more
core   +1 more source

Overview of the JET ITER-like wall divertor

open access: yesNuclear Materials and Energy, 2017
The work presented draws on new analysis of components removed following the second JET ITER-like wall campaign 2013–14 concentrating on the upper inner divertor, inner and outer divertor corners, lifetime issues relating to tungsten coatings on JET ...
A. Widdowson   +16 more
doaj   +1 more source

Design of a multi-configurations divertor for the DTT facility

open access: yesNuclear Materials and Energy, 2022
The standard positive triangularity H-mode tokamak operation with Single Null Divertor (SND) configuration and tungsten monoblocks targets can face some difficulties in providing a solution scalable towards the realization of the fusion reactor.
P. Innocente   +8 more
doaj   +1 more source

Design of the divertor and power exhaust scenarios development for the Divertor Tokamak Test facility

open access: yes, 2022
The new high field superconducting divertor tokamak test facility (DTT) [1] presently under construction is devoted to specifically study power exhaust solutions in regimes as close as possible to those foreseen in DEMO fusion reactor in terms of power ...
Innocente P   +10 more
core  

Survey of tungsten gross erosion from main plasma facing components in WEST during a L-mode high fluence campaign

open access: yesNuclear Materials and Energy
An initial high fluence campaign was performed in WEST, in 2023, on the newly installed actively cooled tungsten divertor composed of ITER-grade monoblocks.
N. Fedorczak   +15 more
doaj   +1 more source

Turning Bonding Into Function: The Emerging Role of the Bioactive Selenium─Metal Motif in Toxicology and Medicinal Chemistry

open access: yesChemistry – A European Journal, EarlyView.
Balancing Act: Se─M bond serving as the fulcrum of the balance scale to compare the different weight of toxicity and therapeutic effects in biological environment. ABSTRACT The synthesis and characterization of organo‐selenium compounds have attracted considerable interest for decades, driven by the search for efficient catalysts and bioinspired ...
Matteo Filippi   +6 more
wiley   +1 more source

Evaluation of the predictive accuracy of tungsten erosion evolution on divertor plates in the large helical device using ERO2.0

open access: yesNuclear Materials and Energy
The predictive accuracy of the three-dimensional Monte Carlo-based plasma-surface interaction code ERO2.0 was evaluated through simulations of tungsten erosion on tungsten-coated divertor plates in the closed helical divertor of LHD during an ...
M. Shoji   +7 more
doaj   +1 more source

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