Results 91 to 100 of about 304,251 (189)

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

Nuclear 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, V. Rozhansky, E. Kaveeva, V. Korzueva, I. Senichenkov, I. Veselova, R.A. Pitts, X. Bonnin   +7 more
doaj   +1 more source

Characterization of 3-strap antennas in ASDEX Upgrade

EPJ Web of Conferences, 2017
The response of the local RF current measured at limiters of 3-strap ICRF antenna to variations of power balance and phasing at fICRF=30MHz agrees qualitatively well with EM calculations by TOPICA and RAPLICASOL codes. Measurements of tungsten sputtering
Bobkov Volodymyr, Bilato Roberto, Colas Laurent, Dux Ralph, Faudot Eric, Faugel Helmut, Fünfgelder Helmut, Herrmann Albrecht, Jacquot Jonathan, Kallenbach Arne, Milanesio Daniele, Maggiora Riccardo, Neu Rudolf, Noterdaeme Jean-Marie, Ochoukov Roman, Pütterich Thomas, Tierens Wouter, Zhang Wei   +17 more
doaj   +1 more source

Review on ASDEX Upgrade operation with tungsten plasma facing components

Nuclear Materials and Energy
With the decision of ITER to start its operation with tungsten as plasma facing material also for the main chamber plasma facing components, the interest in the consequences of the use of W was strongly increased. Although many investigations had already
R. Neu, C. Angioni, V. Bobkov, R. Dux, J. Hobirk, A. Kallenbach, K. Krieger, T. Pütterich, V. Rohde, K. Schmid   +9 more
doaj   +1 more source

Chemically assisted physical sputtering of Tungsten: Identification via the 6Π→6Σ+ transition of WD in TEXTOR and ASDEX Upgrade plasmas

Nuclear Materials and Energy, 2019
Tungsten (W) is a preferred plasma-facing material for areas of high particle and power impact in present day and future fusion devices. The lifetime of W plasma-facing components (PFCs) under steady-state conditions is limited by erosion processes ...
S. Brezinsek, A. Pospieszczyk, G. Sergienko, R. Dux, M. Cavedon, M. Faitsch, K. Krieger   +6 more
doaj   +1 more source

A practical protocol to emulate a reactor scenario on present machines, with application to the ASDEX Upgrade tokamak via predictive modeling

Nuclear Fusion, 2023
In this work, a novel practical strategy to emulate a reactor scenario on present tokamak experiments is presented. A recipe how to scale several relevant parameters from a hypothetical reactor scenario down to present devices is discussed.
E. Fable, P. David, O. Kudlacek, C. Hopf, B. Sieglin, J. Stober, W. Treutterer, M. Weiland, C. Wu, H. Zohm, the ASDEX Upgrade Team   +10 more
doaj   +1 more source

Fast-ion pressure dominating the mass dependence of the core heat transport in ASDEX Upgrade H-modes

, 2021
H-mode plasmas in ASDEX Upgrade (AUG) using different hydrogen isotopes are analysed with respect to their core transport properties. The experimental results are discussed and we present gyrokinetic simulations which are able to reproduce the ...
P. Schneider, N. Bonanomi, C. Angioni, M. Weiland, M. Cavedon, P. David, R. Fischer, P. Hennequin, J. Hobirk, A. Kappatou, B. Kurzan, R. McDermott, U. Plank, T. Pütterich, F. Ryter, M. Willensdorfer, the ASDEX Upgrade team, and the EUROfusion MST1 Team   +17 more
semanticscholar   +1 more source

The quasi-continuous exhaust regime in JET

Nuclear Fusion
The quasi-continuous exhaust (QCE) regime is a regime that is naturally type-I ELM-free. It combines the high density at the plasma edge needed for power exhaust with the high normalised energy confinement typical for H-mode operation.
M. Faitsch, M. Dunne, E. Lerche, P. Lomas, I. Balboa, P. Bilkova, P. Bohm, A. Kappatou, D. Kos, B. Labit, S. Menmuir, O. Sauter, S. Silburn, E.R. Solano, H.J. Sun, A. Tookey, E. Viezzer, U. Stroth, JET Contributors, the EUROfusion Tokamak Exploitation Team   +19 more
doaj   +1 more source

Extension of electron cyclotron heating at ASDEX Upgrade with respect to high density operation

EPJ Web of Conferences, 2017
The ASDEX Upgrade electron cyclotron resonance heating operates at 105 GHz and 140 GHz with flexible launching geometry and polarization. In 2016 four Gyrotrons with 10 sec pulse length and output power close to 1 MW per unit were available.
Schubert Martin, Stober Jörg, Herrmann Albrecht, Kasparek Walter, Leuterer Fritz, Monaco Francesco, Petzold Bernhard, Plaum Burkhard, Vorbrugg Stefan, Wagner Dietmar, Zohm Hartmut   +10 more
doaj   +1 more source

Stationary ELM-free H-mode in ASDEX Upgrade

Nuclear Fusion, 2020
A stationary H-mode without edge localized modes (ELMs) has been recently achieved in the ASDEX Upgrade tokamak by applying central electron cyclotron resonance heating above the L-H power threshold with adequate fueling.
L. Gil, C. Silva, T. Happel, G. Birkenmeier, M. Cavedon, G. Conway, L. Guimarais, T. Pütterich, J. L. Santos, M. Schubert, E. Seliunin, A. Silva, J. Stober, U. Stroth, E. Trier, E. Wolfrum, E. Team   +16 more
semanticscholar   +1 more source

The upgraded ASDEX Upgrade contribution to the ITPA confinement database: description and analysis

, 2021
The ITPA multi-machine confinement database has been recently extended, in particular to account for the effect of the metallic plasma facing components installed in the ASDEX Upgrade and JET tokamaks during the last decade.
F. Ryter, C. Angioni, G. Tardini, G. Birkenmeier, P. David, M. Dunne, R. Fischer, T. Pütterich, J. Schweinzer, J. Stober, the ASDEX Upgrade team, the EUROfusion MST1 team   +11 more
semanticscholar   +1 more source