Results 41 to 50 of about 242,206 (161)

ITER-like current ramps in JET with ILW: experiments, modelling and consequences for ITER [PDF]

open access: yes, 2015
Since the ITER-like wall in JET (JET-ILW) came into operation, dedicated ITER-like plasma current (I-p) ramp-up (RU) and ramp-down (RD) experiments have been performed and matched to similar discharges with the carbon wall (JET-C).
Sips, A.C.C.   +27 more
core   +1 more source

Impact of ICRF on the scrape-off layer and on plasma wall interactions: From present experiments to fusion reactor

open access: yesNuclear Materials and Energy, 2019
Recent achievements in studies of the effects of ICRF (Ion Cyclotron Range of Frequencies) power on the SOL (Scrape-Off Layer) and PWI (Plasma Wall Interactions) in ASDEX Upgrade (AUG), Alcator C-Mod, and JET-ILW are reviewed.
V. Bobkov   +30 more
doaj   +1 more source

Isotope mass dependence of pedestal transport in JET H-mode plasmas

open access: yesNuclear Fusion, 2023
We present a comparative transport analysis of the isotope mass dependence in the pedestal of two pairs of deuterium/hydrogen type I ELMy H-mode discharges in JET with ITER-like wall, one characterized by the same input power, the other one by the same ...
I. Predebon   +8 more
doaj   +1 more source

A study of the atomic and molecular power loss terms in EDGE2D-EIRENE simulations of JET ITER-like wall L-mode discharges

open access: yesNuclear Materials and Energy, 2017
A discrepancy in the divertor radiated powers between EDGE2D-EIRENE simulations and JET-ILW experiments employing a set of NBI-heated L-mode discharges with step-wise density variation is investigated.
K.D. Lawson   +13 more
doaj   +1 more source

EFD-C(13)03/46 Comparisons Between EDGE2D/EIRENE Simulations and D and Low Z Impurity Spectral Emission from JET ITER-like Wall L-mode Plasmas [PDF]

open access: yes, 2013
An understanding of the behaviour of the plasma edge and divertor physics is essential for the design of next-step machines such as ITER, for which JET with its ITER-Like Wall (ILW) of Be in the main chamber and W in the divertor is ideally suited.
Contributors, JET-EFDA   +32 more
core   +1 more source

EFD-C(13)03/29 ELM Energy Losses in Baseline Plasma in JET with the ILW Compared to the CFC First-Wall

open access: yes, 2013
The baseline type I ELMy H-mode scenario has been re-established in JET with the new tungsten MKII-HD divertor and beryllium-main wall (hereafter called ITER-like wall, ILW).
T. Eich   +28 more
core   +1 more source

Influence of the impurities in the hybrid discharges with high power in JET ILW

open access: yesNuclear Fusion, 2022
Abstract The aim of this paper is to numerically study the influences of the impurities on the high power hybrid discharges in the JET ITER-like wall (ILW) configuration in the DD and deuterium–tritium (DT) scenarios. Numerical simulations with the COREDIV code of hybrid discharges with 32 MW auxiliary heating, 2.2 MA plasma current and ...
I. Ivanova-Stanik   +9 more
openaire   +4 more sources

The Role of Combined ICRF and NBI Heating in JET Hybrid Plasmas in Quest for High D-T Fusion Yield

open access: yesEPJ Web of Conferences, 2017
Combined ICRF and NBI heating played a key role in achieving the world-record fusion yield in the first deuterium-tritium campaign at the JET tokamak in 1997.
Mantsinen Mervi   +21 more
doaj   +1 more source

Fuel desorption from JET-ILW materials: assessment of analytical approach and identification of sources of uncertainty and discrepancy

open access: yesNuclear Fusion, 2023
This work was carried out to identify sources of errors, uncertainties and discrepancies in studies of fuel retention in wall components from the JET tokamak using methods based on thermal desorption.
Y. Zayachuk   +14 more
doaj   +1 more source

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
N. Catarino   +8 more
doaj   +1 more source

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