Results 1 to 10 of about 166 (115)

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.
A. Huber   +19 more
doaj   +9 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

L-H transition studies in tritium and deuterium–tritium campaigns at JET with Be wall and W divertor

open access: yesNuclear Fusion, 2023
The recent deuterium–tritium campaign in JET-ILW (DTE2) has provided a unique opportunity to study the isotope dependence of the L-H power threshold in an ITER-like wall environment (Be wall and W divertor).
E.R. Solano   +86 more
doaj   +1 more source

Erosion at the inner wall of JET during the discharge campaign 2013–2014

open access: yesNuclear Materials and Energy, 2017
The erosion of Be and W marker layers was investigated using long-term samples containing marker layers during the second ITER-like wall discharge campaign 2013–2014 (ILW-2).
S. Krat   +6 more
doaj   +1 more source

Tritium retention characteristics in dust particles in JET with ITER-like wall

open access: yesNuclear Materials and Energy, 2018
A tritium imaging plate technique (TIPT) in combination with an electron-probe microscopic analysis (EPMA) were applied to examine tritium (T) retention characteristics in individual dust particles collected in the Joint European Torus with the ITER-like
T. Otsuka   +17 more
doaj   +1 more source

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).
J. Likonen   +9 more
doaj   +1 more source

Deuterium retention in the divertor tiles of JET ITER-Like wall

open access: yesNuclear Materials and Energy, 2017
Divertor tiles removed after the second JET ITER-Like Wall campaign 2013–2014 (ILW-2) were studied using Secondary Ion Mass Spectrometry (SIMS). Measurements show that the thickest beryllium (Be) dominated deposition layers are located at the upper part ...
A. Lahtinen   +9 more
doaj   +1 more source

Recent H majority inverted radio frequency heating scheme experiments in JET-ILW

open access: yesEPJ Web of Conferences, 2017
Inverted 3He and D ion cyclotron minority heating scenarios were recently tested in JET-ILW. They confirm the good heating efficiency at low concentrations of ∼3%. The 3He minority heating scheme is only modestly affected by the change from a carbon (JET-
Van Eester Dirk   +24 more
doaj   +1 more source

EDGE2D-EIRENE simulations of the impact of poloidal flux expansion on the radiative divertor performance in JET

open access: yesNuclear Materials and Energy, 2017
In the past at JET, with the MkI divertor, a systematic study of the influence of X-point height and poloidal flux expansion has been conducted [1,2] showing minor differences in the radiation distribution, whereas in [3] experiment and simulations have ...
B. Viola   +7 more
doaj   +1 more source

Home - About - Disclaimer - Privacy