Results 1 to 10 of about 707,405 (284)

Electron cyclotron heating assisted start-up experiments in J-TEXT [PDF]

open access: yesEPJ Web of Conferences, 2023
Electron cyclotron heating (ECH) breakdown and burn-through assist has been adopted to make the ITER start-up, which uses a low toroidal electric field of about 0.3 V/m, more robust.
Zhang Junli   +14 more
doaj   +1 more source

The development of 1 MW ECRH system on J-TEXT [PDF]

open access: yesEPJ Web of Conferences, 2023
A 1 MW electron cyclotron resonance heating system has been designed and developed for J-TEXT tokamak not only to enhance the total heating power but also to provide another possible way to control the plasma parameters.
Chen Xixuan   +4 more
doaj   +1 more source

Infrared detection of tungsten cracking on actively cooled ITER-like component during high power experiment in WEST

open access: yesNuclear Materials and Energy, 2023
The consequences of tungsten (W) damaging processes, such as cracking and melting, on divertor lifetime and plasma operation are high priority issues for ITER.
Q. Tichit   +16 more
doaj   +1 more source

Very high-resolution infrared imagery of misaligned tungsten monoblock edge heating in the WEST tokamak

open access: yesNuclear Materials and Energy, 2021
Fourteen ITER-like plasma-facing units (PFUs) made of bulk tungsten were installed in the WEST tokamak divertor. Five of which were misaligned with their poloidal leading edges (LEs) exposed to the plasma heat flux: two sharp-edge PFUs and three ...
A. Grosjean   +18 more
doaj   +1 more source

Testing of ITER-grade plasma facing units in the WEST tokamak: Progress in understanding heat loading and damage mechanisms

open access: yesNuclear Materials and Energy, 2023
Assessing the performance of the ITER design for the tungsten (W) divertor Plasma Facing Units (PFUs) in a tokamak environment is a high priority issue to ensure efficient plasma operation.
Y. Corre   +22 more
doaj   +1 more source

Plasma exposure of a pre-damaged ITER-like plasma facing unit in the WEST tokamak: in-situ and post-mortem measurements

open access: yesNuclear Materials and Energy, 2023
The consequences of tungsten (W) cracking on divertor lifetime and plasma operation are high priority issues for ITER. One actively cooled ITER-like plasma facing unit (PFU) has been pre-damaged in a High Heat Flux (HHF) facility before its installation ...
Yann Corre   +19 more
doaj   +1 more source

Permeation and trapping of hydrogen in Eurofer97

open access: yesNuclear Materials and Energy, 2021
Diffusion and trapping of hydrogen isotopes in fusion materials need to be fully described in order to evaluate permeation and retention in fusion reactors walls and breeding blankets.
F. Montupet-Leblond   +9 more
doaj   +1 more source

Project Design of a Pulsed D-D Fusion Neutron Source Based on Field Reversed Configuration

open access: yes中国工程科学, 2022
The fusion neutron source is of great significance for conducting material testing for future fusion reactors, as it can genuinely reflect the change of material properties under fusion neutron irradiation.
Pan Yuan   +8 more
doaj   +1 more source

OEDGE modeling of far-SOL tungsten impurity sources and screening in WEST

open access: yesNuclear Materials and Energy, 2022
The plasma background and impurity transport in the scrape-off layer (SOL) of the WEST tokamak are modeled for three discharges over a Psep power scan ranging between 1.5 and 2.35 MW. An extended modeling grid is used to investigate far-SOL sourcing from
J.B. Maeker   +10 more
doaj   +1 more source

Adsorption of Metolachlor and Its Transformation Products, ESA and OXA, on Activated Carbons

open access: yesApplied Sciences, 2021
Three activated carbons from lignocellulosic residues and a commercial carbon have been tested for the removal of the herbicide metolachlor and its two degradation transformation products, named ESA and OXA, in aqueous solutions.
Alicia Gomis-Berenguer   +2 more
doaj   +1 more source

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