Results 91 to 100 of about 451,392 (162)
Understanding tungsten erosion during inter/intra-ELM periods in He-dominated JET-ILW plasmas
Tungsten erosion was quantified during inter/intra-ELM periods in He-dominated JET-ILW plasmas by optical emission spectroscopy. The intra-ELM tungsten sputtering in helium plasmas, which dominates the total W source, prevails by a factor of about 4 over
A. Huber +23 more
semanticscholar +1 more source
N=2 ICRH of H majority plasmas in JET-ILW [PDF]
Heating single ion species plasmas with ICRF is a challenging task: Fundamental ion cyclotron heating (w = wci) suffers from the adverse polarization of the RF electric fields near the majority cyclotron resonance while second harmonic heating (w = 2wci) typically requires pre-heating of the plasma ions to become efficient.
Lerche, E +11 more
openaire +2 more sources
ICRH system performance during ITER-Like Wall operations at JET and the outlook for DT campaign
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
ICRH-related impurity source and control across experiments in H, D, T plasmas at JET-ILW
The experimental and theoretical analysis were focused on experiments conducted to assess the effect of plasma isotopes, protium (H), deuterium (D), and tritium (T) on ion cyclotron resonance heating (ICRH) related plasma wall interactions. Comparison of
A. Chomiczewska +24 more
semanticscholar +1 more source
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
Main chamber wall plasma loads in JET-ITER-like wall at high radiated fraction
Future tokamak reactors of conventional design will require high levels of exhaust power dissipation (more than 90% of the input power) if power densities at the divertor targets are to remain compatible with active cooling.
C. Guillemaut +22 more
doaj +1 more source
Experimental campaigns at the Joint European Torus with an ITER-like Be/W wall with pure deuterium (D), tritium (T), and deuterium–tritium (DT) were a unique opportunity to explore various aspects related to the ITER operation.
N. Wendler +12 more
semanticscholar +1 more source
Density pedestal prediction model for tokamak plasmas
A model for the pedestal density prediction based on neutral penetration combined with pedestal transport is presented. The model is tested against a pedestal database of JET-ILW Type I ELMy H-modes showing good agreement over a wide range of parameters ...
S. Saarelma +20 more
doaj +1 more source
40 years of ICRF operation on JET: Challenges and achievements [PDF]
After 40 years of successful operation and multiple Deuterium-Tritium (D-T) campaigns, the Joint European Torus (JET) concluded its operations in December 2023.
Dumortier Pierre +9 more
doaj +1 more source
Comparison of DIVIMP and EDGE2D-EIRENE tungsten transport predictions in JET edge plasmas
The average tungsten concentrations in the pedestal region (cW) predicted by the Monte Carlo code DIVIMP and the coupled multi-fluid plasma/kinetic neutral code EDGE2D-EIRENE are found to agree within a factor of 2 for a range of JET-ILW L-mode and H ...
H.A. Kumpulainen +5 more
doaj +1 more source

