Zobrazeno 1 - 10
of 717
pro vyhledávání: '"Team, the ASDEX Upgrade"'
A new axisymmetric equilibrium solver has been written, called FEQIS (Flexible EQuIlibrium Solver), which purpose is to be used inside integrated modeling of tokamak plasmas. The FEQIS code solves the Grad-Shafranov equation and the "circuit" equatio
Externí odkaz:
http://arxiv.org/abs/2410.13630
Autor:
Heinrich, Paul, Papp, Gergely, Jachmich, Stefan, Artola, Javier, Bernert, Matthias, de Marné, Pascal, Dibon, Mathias, Dux, Ralph, Eberl, Thomas, Hobirk, Jörg, Lehnen, Michael, Peherstorfer, Tobias, Schwarz, Nina, Sheikh, Umar, Sieglin, Bernhard, Svoboda, Jakub, Team, the ASDEX Upgrade, Team, the EUROfusion Tokamak Exploitation
Future large tokamaks will operate at high plasma currents and high stored plasma energies. To ensure machine protection in case of a sudden loss of plasma confinement (major disruption), a large fraction of the magnetic and thermal energy must be ra
Externí odkaz:
http://arxiv.org/abs/2410.00591
Autor:
Eich, Thomas, Body, Thomas, Faitsch, Michael, Grover, Ondrej, Miller, Marco Andres, Manz, Peter, Looby, Tom, Kuang, Adam Qingyang, Redl, Andreas, Reinke, Matt, Creely, Alex J., Battaglia, Devon, Hillesheim, Jon, Wigram, Mike, Hughes, Jerry W., team, the ASDEX Upgrade
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. In this wor
Externí odkaz:
http://arxiv.org/abs/2407.13539
Autor:
Maris, Andrew, Rea, Cristina, Pau, Alessandro, Hu, Wenhui, Xiao, Bingjia, Granetz, Robert, Marmar, Earl, team, the EUROfusion Tokamak Exploitation, team, the Alcator C-Mod, team, the ASDEX Upgrade, team, the DIII-D, team, the EAST, team, the TCV
The "density limit" is one of the fundamental bounds on tokamak operating space, and is commonly estimated via the empirical Greenwald scaling. This limit has garnered renewed interest in recent years as it has become clear that ITER and many tokamak
Externí odkaz:
http://arxiv.org/abs/2406.18442
Autor:
Heinrich, P., Papp, G., Lauber, Ph., Pautasso, G., Dunne, M., Maraschek, M., Igochine, V., Linder, O., Team, the ASDEX Upgrade, Team, the EUROfusion Tokamak Exploitation
ASDEX Upgrade has developed multiple massive gas injection (MGI) scenarios to investigate runaway electron (RE) dynamics. During the current quench of the MGI induced disruptions, Alfv\'enic activity is observed in the 300-800 kHz range. With the hel
Externí odkaz:
http://arxiv.org/abs/2402.01268
Autor:
Leppin, L. A., Görler, T., Cavedon, M., Dunne, M. G., Wolfrum, E., Jenko, F., Team, the ASDEX Upgrade
The theoretical investigation of relevant turbulent transport mechanisms in H-mode pedestals is a great scientific and numerical challenge. In this study, we address this challenge by global, nonlinear gyrokinetic simulations of a full pedestal up to
Externí odkaz:
http://arxiv.org/abs/2303.10596
Autor:
Cathey, A, Hoelzl, M, Gil, L, Dunne, MG, Harrer, GF, Huijsmans, GTA, Kalis, J, Lackner, K, Pamela, SJP, Wolfrum, E, Günter, S, team, the JOREK, Team, the ASDEX Upgrade, Team, the EUROfusion MST1
Regimes of operation in tokamaks that are devoid of large ELMs have to be better understood to extrapolate their applicability to reactor-relevant devices. This paper describes non-linear extended MHD simulations that use an experimental equilibrium
Externí odkaz:
http://arxiv.org/abs/2301.09066
The High Field High Density Region (HFSFD) has been experimentally observed in both divertor and limiter tokamak devices. In order to numerically reproduced the HFSHD region in the limiter tokamak device J-TEXT, we first performed SOLPS-ITER simulati
Externí odkaz:
http://arxiv.org/abs/2301.04440
Autor:
Di Siena, A., Navarro, A. Banon, Luda, T., Merlo, G., Bergmann, M., Leppin, L., Goerler, T., Parker, J. B., LoDestro, L., Hittinger, J., Dorland, B., Hammett, G., Jenko, F., Team, the ASDEX Upgrade, Team, the EUROfusion MST1
An accurate description of turbulence up to the transport time scale is essential for predicting core plasma profiles and enabling reliable calculations for designing advanced scenarios and future devices. Here, we exploit the gap separation between
Externí odkaz:
http://arxiv.org/abs/2204.05651
Autor:
Rueda-Rueda, J., Garcia-Munoz, M., Viezzer, E., Schneider, P. A., Garcia-Dominguez, J., Ayllon-Guerola, J., Galdon-Quiroga, J., Herrmann, A., Du, X., Van Zeeland, M. A., Oyola, P., Rodriguez-Ramos, M., team, the ASDEX-Upgrade
An Imaging Neutral Particle Analyser (INPA) diagnostic has been designed for the ASDEX Upgrade (AUG) tokamak. The AUG INPA diagnostic will measure fast neutrals escaping the plasma after CX reactions. The neutrals will be ionised by a 20 nm carbon fo
Externí odkaz:
http://arxiv.org/abs/2203.12995