Results 51 to 60 of about 108,499 (193)

Probing non-linear MHD stability of the EDA H-mode in ASDEX Upgrade

open access: yesNuclear Fusion, 2023
Regimes of operation in tokamaks that are devoid of large edge localised modes have to be better understood to extrapolate their applicability to reactor-relevant devices.
A. Cathey   +13 more
doaj   +1 more source

NBI-driven Alfvénic modes at ASDEX Upgrade [PDF]

open access: yes, 2012
A large variety of electromagnetic modes excited by NBI-generated energetic ions are observed in the early phase of many discharges at ASDEX Upgrade. In addition to the well-known reversed shear Alfven eigenmodes (RSAE) and the toroidal Alfven eigenmodes
Maraschek, M.   +13 more
core   +1 more source

Heat transport at the boundary of ASDEX Upgrade [PDF]

open access: yesPlasma Physics and Controlled Fusion, 1997
The flow of heat in the scrape-off layer (SOL) region of ASDEX Upgrade is investigated and compared with simple modelling. Parallel heat transport is found to be consistent with electron heat conduction based on Spitzer - H?rm conductivity. Cross-field heat transport is characterized using radial e-folding distances for power, temperature and plasma ...
Pitcher, C.   +8 more
openaire   +3 more sources

Overview of the EUROfusion Tokamak Exploitation programme in support of ITER and DEMO

open access: yesNuclear Fusion
Within the 9th European Framework programme, since 2021 EUROfusion is operating five tokamaks under the auspices of a single Task Force called ‘Tokamak Exploitation’.
E. Joffrin   +814 more
doaj   +1 more source

The separatrix operational space of next-step fusion experiments: From ASDEX Upgrade data to SPARC scenarios

open access: yesNuclear Materials and Energy
Fusion power plants require ELM-free, detached operation to prevent divertor damage and erosion. The separatrix operational space (SepOS) is proposed as a tool for identifying access to the type-I ELM-free quasi-continuous exhaust regime.
T. Eich   +14 more
doaj   +1 more source

DIVIMP simulations of 13C puffing experiments in ASDEX Upgrade L-mode plasma [PDF]

open access: yes, 2011
Carbon migration has been investigated both experimentally and numerically by injecting isotopically marked methane (13CH4) at trace levels into a series of identical low-density, low-confinement mode discharges at the last day of the 2007 ASDEX Upgrade ...
T. Kurki-Suonio   +20 more
core   +1 more source

Migration of 13C and deposition at ASDEX Upgrade

open access: yes, 2007
To investigate material transport in scrape-off layer plasma and long term deposition in divertor, 13CH4 was puffed at the end of 2004 and 2005 experimental campaigns into ASDEX Upgrade from the outer mid-plane.
Vainonen-Ahlgren, E.   +8 more
core   +1 more source

Reduced models for the maximum vertical force in a tokamak device

open access: yesNuclear Fusion
A formula was suggested in Miyamoto et al (2011 Plasma Phys. Control. Fusion 53 082001) to calculate the total maximum vertical force due to a vertical displacement event in a tokamak device without modeling the whole phenomenon.
G. Pautasso   +2 more
doaj   +1 more source

Maximum likelihood bolometry for ASDEX upgrade experiments [PDF]

open access: yes
Bolometry is an essential diagnostic for calculating the power balances and for the understanding of different physical aspects of tokamak experiments. The reconstruction method based on the Maximum Likelihood (ML) principle, developed initially for JET,
Spolladore, Luca   +10 more
core   +1 more source

Design and stress analysis of in-vessel saddle coils for MHD control in ASDEX Upgrade [PDF]

open access: yes, 2008
A set of in-vessel saddle coils for MHD control in ASDEX Upgrade is described. A conventional coil design is chosen which employs a five turn square cross-section copper conductor with central cooling bore embedded in an epoxy resin.
Herrmann, A.   +7 more
core   +1 more source

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