Results 31 to 40 of about 36,485 (223)
In-situ Low Power Tests of the ASDEX Upgrade ECRH Transmission Lines [PDF]
EPJ Web of ConferencesAn Electron Cyclotron Resonance Heating (ECRH) system employing 8 gyrotrons is in routine operation at the ASDEX Upgrade tokamak at IPP Garching. The gyrotrons are of two-frequency type operating at 105 and 140 GHz with a maximum output power of up to 1 ...
Wagner Dietmar +5 more
doaj +1 more source
Perturbative analysis of low-frequency instabilities in high-field ST40 experiments
Nuclear Fusion, 2023 Linear and nonlinear perturbative analyses of low-frequency instabilities are presented for ST40 spherical torus high field plasmas, with simultaneous neutral beam heating due to two tangential sources at 25 keV and 55 keV.
V.N. Duarte +9 more
doaj +1 more source
Molecules, 2021 In this study, time-dependent, one-dimensional modeling of a surface dielectric barrier discharge (SDBD) device, driven by a sinusoidal voltage of amplitude 1–3 kV at 20 kHz, in argon is described. An SDBD device with two Cu-stripe electrodes, covered by
Taj Muhammad Khan +3 more
doaj +1 more source
Evaluation of the functional acceptability of the ITER vacuum vessel
Nuclear Fusion, 2022 The International Thermonuclear Experimental Reactor (ITER) vacuum vessel (VV) is one of the critical components of the ITER tokamak fusion reactor. The first sector of the ITER VV was delivered to ITER Organization in 2020, and it is ready to assemble ...
Hokyu Moon +3 more
doaj +1 more source
MHD Instabilities in Tokamaks [PDF]
Fusion Science and Technology, 2006 A general introduction to ideal magnetohydrodynamic (MHD) stability of tokamak plasmas is given, using linear perturbations of the ideal MHD equations.
openaire +4 more sources
DTT - Divertor Tokamak Test facility - Interim Design Report [PDF]
, 2019 The “Divertor Tokamak Test facility, DTT” is a milestone along the international program aimed at demonstrating – in the second half of this century – the feasibility of obtaining to commercial electricity from controlled thermonuclear fusion.DTT is a ...
Affinito L. +5 more
core +2 more sources
Plasma boundary reconstruction and shape control of Tokamak discharges in RFX-mod [PDF]
, 2011 La tesi si occupa del controllo di forma del plasma in configurazione Tokamak a doppio nullo nell’esperimento RFX-mod. Vengono affrontate problematiche di ricostruzione della forma, con un apporto originale nell’utilizzo di una interpolante thin plate ...
Merlo, Pierangelo
core
Initial analytical theory of plasma disruption and experimental evidence
Scientific Reports, 2023 It is a great physical challenge to achieve controlled nuclear fusion in magnetic confinement tokamak and solve energy shortage problem for decades. In tokamak plasma, large-scale plasma instability called disruption will halt power production of reactor
Huibin Qiu +13 more
doaj +1 more source
First SOLPS‐ITER Simulation Study of Japanese DEMO on Leakage of Seeded Ar Impurity
Contributions to Plasma Physics, EarlyView.ABSTRACT For JA DEMO, one of the grand challenges is efficiently handling the extreme power loads onto plasma‐facing components, particularly the divertor targets. Impurity seeding is an essential strategy for increasing the radiation losses and thereby reducing the heat load on the targets.
Hang Si +6 more
wiley +1 more source
Inferring the scrape-off layer heat flux width in a divertor with a low degree of axisymmetry
Nuclear Materials and EnergyPlasma facing components (PFCs) in the next generation of tokamak devices will operate in challenging environments, with heat loads predicted to exceed 10 MW/m2. The magnitude of these heat loads is set by the width of the channel, the ‘scrape-off layer’
C. Marsden +8 more
doaj +1 more source