Results 71 to 80 of about 1,720 (162)

Composition of electron temperature gradient driven plasma turbulence in JET-ILW tokamak plasmas

open access: yesPhysical Review Research
This letter reports on new fundamental insights into small scale plasma turbulence that is responsible for confinement degradation on the JET tokamak. We compare the structure of electron temperature gradient (ETG) driven turbulence in the edge region of
B. Chapman-Oplopoiou   +4 more
doaj   +1 more source

Parameter dependencies of the experimental nitrogen concentration required for detachment on ASDEX Upgrade and JET

open access: yesNuclear Materials and Energy, 2021
While current tokamak experiments are beginning to use real-time feedback control systems to manage the plasma exhaust, future tokamaks still require validation of theoretical models used to predict the threshold impurity concentration required to ...
S.S. Henderson   +20 more
doaj   +1 more source

Laser cleaning of diagnostic mirrors from tungsten-oxygen tokamak-like contaminants [PDF]

open access: yes, 2016
This paper presents a laboratory-scale experimental investigation about the laser cleaning of diagnostic first mirrors from tokamak-like contaminants, made of oxidized tungsten compounds with different properties and morphology.
Dellasega, David   +3 more
core   +1 more source

Impact of W events and dust on JET-ILW operation [PDF]

open access: yesJournal of Nuclear Materials, 2015
The occurrence of transient impurity events (TIE) leading to intense radiation spikes in JET plasma discharges has been studied since the installation of the ITER-like wall (ILW). To generate the observed average increase in radiated power of 1.5 MW, a spherical particle of solid W of radius >90 μm would be required. The drop in plasma energy caused
Sertoli, M.   +13 more
openaire   +5 more sources

ICRH system performance during ITER-Like Wall operations at JET and the outlook for DT campaign

open access: yesEPJ Web of Conferences, 2017
Performance of JET ICRH system since installation of the metal ITER-Like Wall (ILW) has been assessed statistically. The data demonstrate steady increase of the RF power coupled to plasmas over recent years with the maximum pulse-average and peak values ...
Monakhov Igor   +6 more
doaj   +1 more source

Impact of ICRF on the scrape-off layer and on plasma wall interactions: From present experiments to fusion reactor [PDF]

open access: yes, 2020
Recent achievements in studies of the effects of ICRF (Ion Cyclotron Range of Frequencies) power on the SOL (Scrape-Off Layer) and PWI (Plasma Wall Interactions) in ASDEX Upgrade (AUG), Alcator C-Mod, and JET-ILW are reviewed.
Abduallev, S.   +1255 more
core   +2 more sources

Thermal annealing and exposure to divertor-like deuterium plasma of tailored tungsten oxide coatings [PDF]

open access: yes, 2015
In this work we produced tungsten (W) and W oxide (WOx) films by pulsed laser deposition (PLD) with the aim of the addressing modifications of structure and morphology that occur after annealing treatments and high-flux deuterium plasma.
Dellasega, D.   +5 more
core   +1 more source

Divertor currents optimization procedure for JET-ILW high flux expansion experiments [PDF]

open access: yesFusion Engineering and Design, 2018
This paper deals with a divertor coil currents optimized procedure to design High Flux Expansion (HFE) configurations in the JET tokamak aimed to study the effects of flux expansion variation on the radiation fraction and radiated power re-distribution.
Calabrò, G.   +222 more
openaire   +4 more sources

An analytical expression for ion velocities at the wall including the sheath electric field and surface biasing for erosion modeling at JET ILW

open access: yesNuclear Materials and Energy, 2017
For simulation of plasma-facing component erosion in fusion experiments, an analytical expression for the ion velocity just before the surface impact including the local electric field and an optional surface biasing effect is suggested.
I. Borodkina   +15 more
doaj   +1 more source

Plasma cleaning of ITER first mirrors in magnetic field

open access: yes, 2014
To avoid reflectivity losses in ITER optical diagnostic systems, plasma sputtering of metallic First Mirrors is foreseen in order to remove deposits coming from the main wall (mainly beryllium and tungsten). Therefore plasma cleaning has to work on large
Leipold, Frank   +5 more
core   +1 more source

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