Results 81 to 90 of about 416,653 (194)

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

Recent progress in modeling ICRF-edge plasma interactions with application to ASDEX Upgrade

open access: yesNuclear Fusion, 2021
This paper summarizes recent progress in modeling the interaction between ion cyclotron range of frequency (ICRF) waves and edge plasma with application to ASDEX Upgrade.
W. Zhang   +13 more
semanticscholar   +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

Validation of a full-plasma integrated modeling approach on ASDEX Upgrade

open access: yesNuclear Fusion, 2021
In this work we present the extensive validation of a refined version of the integrated model based on engineering parameters (IMEP) introduced in reference (Luda et al 2020 Nucl. Fusion 60 036023).
T. Luda   +11 more
semanticscholar   +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

First SOLPS-ITER modelling of an X-point radiator in ITER

open access: yesNuclear Fusion
For the first time, an X -point radiating (XPR) regime using neon (Ne) seed impurity has been obtained in ITER modelling with the SOLPS-ITER code, including fluid drifts.
A. Poletaeva   +7 more
doaj   +1 more source

A study on the density shoulder formation in the SOL of H-mode plasmas

open access: yesNuclear Materials and Energy, 2017
The term “shoulder formation” refers to an increase of the density decay length in the scrape-off layer (SOL) observed in many tokamaks during L-mode operation when a density threshold is reached.
D. Carralero   +11 more
doaj   +1 more source

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