Results 71 to 80 of about 242,206 (161)
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
EFD-P(13)63 Effect of Nitrogen Seeding on the ELM Energy Losses in JET with the ITER-Like Wall
The baseline type I ELMy H-mode scenario has been re-established in JET with the new tungsten MKII-HD divertor and beryllium on the main wall (hereafter called ITER-like wall, JET-ILW).
P. Lomas +17 more
core +1 more source
Determination of Be sputtering yields from the spectroscopic observations at JET ILW based on 3D ERO modelling [PDF]
Estimations of the ITER first wall (FW) lifetime, previously made using the three-dimensional Monte-Carlo ERO code (Borodin et al 2011 Phys. Scr. T145 014008), depend strongly on the assumptions of the physical sputtering yield for beryllium (Be).
Lisgo, S. +18 more
core +1 more source
Tritium removal from JET-ILW after T and D–T experimental campaigns
After the second Deuterium–Tritium Campaign (DTE2) in the JET tokamak with the ITER-Like Wall (ILW) and full tritium campaigns that preceded and followed after the DTE2, a sequence of fuel recovery methods was applied to promote tritium removal from wall
D. Matveev +41 more
doaj +1 more source
Global and pedestal confinement in JET with a Be/W metallic wall
Type I ELMy H-mode operation in JET with the ITER-like Be/W wall (JET-ILW) generally occurs at lower pedestal pressures compared to those with the full carbon wall (JET-C).
Solano, E. R. +51 more
core +1 more source
Beryllium Migration in JET ITER-like Wall Plasmas [PDF]
JET is used as a test bed for ITER, to investigate beryllium migration which connects the lifetime of first-wall components under erosion with tokamak safety, in relation to long-term fuel retention.
Petersson, P. +43 more
core +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
Isotope identity experiments in JET-ILW with H and D L-mode plasmas
NBI-heated L-mode plasmas have been obtained in JET with the Be/W ITER-like wall (JET-ILW) in H and D, with matched profiles of the dimensionless plasma parameters, ρ ∗, ν ∗, β and q in the plasma core confinement region and same T i/T e and Z eff.
Maggi C. F. ; Weisen H. ; Casson F. J. ; Auriemma F. ; Lorenzini R. ; Nordman H. ; Delabie E. ; Eriksson F. ; Flanagan J. ; Keeling D. ; King D. ; Horvath L. ; Menmuir S. ; Salmi A. ; Sips G. ; Tala T. ; Voitsekhovich I. +1 more
core +1 more source
Spectra of magnetic perturbations triggered by pellets in JET plasmas [PDF]
Aiming at investigating edge localised mode (ELM) pacing for future application on ITER, experiments have been conducted on JET injecting pellets in different plasma configurations, including high confinement regimes with type-I and type-III ELMs, low ...
Poli, F. +23 more
core +1 more source
EFD-C(13)03/03 Power Load Studies in JET and ASDEX Upgrade with Full-W Divertors
For the design and the operation of large fusion devices a detailed understanding of the power exhaust processes is necessary. This paper will give an overview of the current research on the divertor power load mechanisms.
T. Eich +17 more
core +1 more source

