Results 21 to 30 of about 90,764 (192)
The risk of metallic armour melting constitutes a major concern for ITER and DEMO. Combined computational and experimental effort has led to a successful understanding of melt dynamics in present-day tokamaks, but there remain unexplored melting regimes ...
S. Ratynskaia +9 more
doaj +1 more source
The ASDEX Upgrade discharge schedule [PDF]
Abstract ASDEX Upgrade's recently commissioned discharge control system (DCS) marks the transition from a traditional programmed system to a highly flexible “data driven” one. The allocation of application processes (APs) to controllers, the interconnection of APs through uniquely named signals, and AP control parameter values are all defined as data,
Neu, G. +5 more
openaire +2 more sources
Fusion Materials Development at Forschungszentrum Jülich
In fusion material research, the focus has been twofold‐plasma facing and structural materials allowing to withstand the extreme conditions such as neutron bombardment and high heat fluxes. In this contribution, the background for the choice of tungsten as first wall material is given and the advanced materials developed at Forschungszentrum Jülich ...
Jan Willem Coenen
wiley +1 more source
Impact of drifts in the ASDEX upgrade upper open divertor using SOLPS‐ITER
Abstract SOLPS‐ITER L‐mode‐like simulations with the full set of currents and drift velocities activated, and fluid neutrals have been carried out to interpret experimental results obtained in AUG. Drifts are critical to quantitatively reproduce the experimental results; however, simulations without drifts can also reproduce some trends qualitatively ...
I. Paradela Pérez +9 more
wiley +1 more source
Previous simulation results for the tokamak ASDEX Upgrade have shown that Magnetic Perturbation (MP) fields could lead to a decrease of the peak heat flux onto the divertor targets. However, experimentally, such a decrease has not been observed.
D. Brida +7 more
doaj +1 more source
Experiences with a solid tungsten divertor in ASDEX Upgrade
In 2013 a redesigned solid tungsten divertor, Div-III, was installed in ASDEX Upgrade. In two experimental campaigns more than 2700 plasma discharges with up to 10s duration, 110MJ plasma heating, and reaching a Psep/R of 10MW/m were conducted.
A. Herrmann +8 more
doaj +1 more source
Pellet-fueled I-mode plasmas in ASDEX Upgrade
This letter reports on the efforts carried out at the ASDEX Upgrade tokamak to integrate I-mode plasmas with pellet fueling and to increase the I-mode Greenwald fraction $f_{\mathrm{GW}}$ , two important requirements for any DEMO operational scenario ...
D. Silvagni +12 more
doaj +1 more source
Induced microwave scattering in the ITER edge transport barrier at ECRH and possibility of its modeling at ASDEX-Upgrade [PDF]
The induced scattering parametric decay instability of O-mode polarized microwaves leading to excitation of lower hybrid or electron plasma waves localized within a tokamak edge transport barrier is investigated.
Gusakov Evgeniy +2 more
doaj +1 more source
Carbon erosion and deposition on the ASDEX Upgrade divertor tiles [PDF]
Carbon deposition and erosion were measured on ASDEX Upgrade divertor tiles and below the roof baffle during the operation period 2002/2003. The inner divertor is a net carbon deposition area, while a large fraction of the outer divertor is erosion ...
Vainonen-Ahlgren, E. +9 more
core +1 more source
Upgrading the ICRF data acquisition system at ASDEX Upgrade [PDF]
The ICRF system at ASDEX Upgrade has proved to be very flexible in use, from high power heating down to moderate or low power levels needed for vessel conditioning. As a consequence of these wide varieties of applications the present capabilities of the data acquisition system became a limiting factor, as the CAMAC system could only record up to about ...
H. Faugel +5 more
openaire +2 more sources

