Results 1 to 10 of about 326,732 (142)

Sawtooth pacing with on-axis ICRH modulation in JET-ILW [PDF]

open access: yesNuclear Fusion, 2017
A novel technique for sawteeth control in tokamak plasmas using ion-cyclotron resonance heating (ICRH) has been developed in the JET-ILW tokamak [2].
Andrea Murari   +2 more
exaly   +9 more sources

The radiated power limit in impurity seeded JET-ILW plasmas

open access: yesNuclear Materials and Energy, 2022
The total radiated fraction is examined in high density H-mode plasmas (Greenwald fraction of about 85 %) in JET by the variation of the auxiliary heating power of Pheat = 14 MW-29 MW.
C Lowry, G F Matthews, A G Meigs
exaly   +4 more sources

Beryllium global erosion and deposition at JET-ILW simulated with ERO2.0

open access: yesNuclear Materials and Energy, 2019
The recently developed Monte-Carlo code ERO2.0 is applied to the modelling of limited and diverted discharges at JET with the ITER-like wall (ILW). The global beryllium (Be) erosion and deposition is simulated and compared to experimental results from ...
Mathias Groth   +2 more
exaly   +16 more sources

Investigation of deuterium trapping and release in the JET divertor during the third ILW campaign using TDS

open access: yesNuclear Materials and Energy, 2019
Selected set of samples from JET ITER-Like Wall (JET-ILW) divertor tiles exposed in 2015–2016 has been analysed using Thermal Desorption Spectrometry (TDS).
Jari Likonen   +2 more
exaly   +3 more sources

First mirror test in JET for ITER: Complete overview after three ILW campaigns

open access: yesNuclear Materials and Energy, 2019
The First Mirror Test for ITER has been carried out in JET with mirrors exposed during: (i) the third ILW campaign (ILW-3, 2015–2016, 23.33 h plasma) and (ii) all three campaigns, i.e. ILW-1 to ILW-3: 2011–2016, 63,52 h in total.
Andrey Litnovsky   +2 more
exaly   +3 more sources

Modelling of tungsten erosion and deposition in the divertor of JET-ILW in comparison to experimental findings

open access: yesNuclear Materials and Energy, 2019
The erosion, transport and deposition of tungsten in the outer divertor of JET-ILW has been studied for an H-Mode discharge with low frequency ELMs.
Mathias Groth   +2 more
exaly   +3 more sources

Assessment of erosion, deposition and fuel retention in the JET-ILW divertor from ion beam analysis data

open access: yesNuclear Materials and Energy, 2017
Post-mortem analyses of individual components provide relevant information on plasma-surface interactions like tungsten erosion, beryllium deposition and plasma fuel retention with divertor tiles via implantation or co-deposition. Ion Beam techniques are
Victoria Corregidor   +2 more
exaly   +3 more sources

Determination of tungsten sources in the JET-ILW divertor by spectroscopic imaging in the presence of a strong plasma continuum

open access: yesNuclear Materials and Energy, 2019
The identification of the sources of atomic tungsten and the measurement of their radiation distribution in front of all plasma-facing components has been performed in JET with the help of two digital cameras with the same two-dimensional view, equipped ...
Petter Ström   +2 more
exaly   +3 more sources

Comparison of JET inner wall erosion in the first three ITER-like wall campaigns

open access: yesNuclear Materials and Energy, 2021
The net erosion of material from recessed areas of the JET main chamber inner wall during the first three ITER-like wall (JET-ILW) campaigns was studied using long-term samples with Be and W marker layers.
S. Krat   +7 more
doaj   +1 more source

Overview of tritium retention in divertor tiles and dust particles from the JET tokamak with the ITER-like wall

open access: yesNuclear Fusion, 2023
Divertor tiles after Joint European Torus-ITER like wall (JET-ILW) campaigns and dust collected after JET-C and JET-ILW operation were examined by a set of complementary techniques (full combustion and radiography) to determine the total, specific and ...
Y. Torikai   +17 more
doaj   +1 more source

Home - About - Disclaimer - Privacy