Results 51 to 60 of about 387 (143)

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

Nuclear 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, T. Body, M. Faitsch, O. Grover, M.A. Miller, P. Manz, T. Looby, A.Q. Kuang, A. Redl, M. Reinke, A.J. Creely, D. Battaglia, J. Hillesheim, M. Wigram, J.W. Hughes   +14 more
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The X-Point radiating regime at ASDEX Upgrade and TCV

Nuclear Materials and Energy, 2023
Future fusion reactors require a safe, steady-state divertor operation. With deep divertor detachment, which is typically induced by impurity seeding, the radiation concentrates in a small region at the X-point or on closed flux surfaces above the X ...
M. Bernert, S. Wiesen, O. Février, A. Kallenbach, J.T.W. Koenders, B. Sieglin, U. Stroth, T.O.S.J. Bosman, D. Brida, M. Cavedon, P. David, M.G. Dunne, S. Henderson, B. Kool, T. Lunt, R.M. McDermott, O. Pan, A. Perek, H. Reimerdes, U. Sheikh, C. Theiler, M. van Berkel, T. Wijkamp, M. Wischmeier   +23 more
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Reduced models for the maximum vertical force in a tokamak device

Nuclear 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, E. Fable, the ASDEX Upgrade Team   +2 more
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A study on the density shoulder formation in the SOL of H-mode plasmas

Nuclear 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, J. Madsen, S.A. Artene, M. Bernert, G. Birkenmeier, T. Eich, G. Fuchert, F. Laggner, V. Naulin, P. Manz, N. Vianello, E. Wolfrum   +11 more
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Overview of initial negative triangularity plasma studies on the ASDEX Upgrade tokamak

Nuclear Fusion, 2022
An overview of results of negative triangularity (NT) studies from the ASDEX Upgrade tokamak (AUG) is given. Moderate values of the triangularity in the range of δ _average ≈ −0.2 have been obtained.
T. Happel, T. Pütterich, D. Told, M. Dunne, R. Fischer, J. Hobirk, R.M. McDermott, U. Plank, ASDEX Upgrade Team the   +8 more
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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
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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
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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
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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
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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