Results 71 to 80 of about 249 (122)

SOLPS-ITER modelling of ASDEX Upgrade L-mode detachment

, 2020
L'abstract è presente nell'allegato / the abstract is in the ...
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Comparison of divertor seed impurity gases retention efficiency by SOLPS-ITER modeling

Nuclear Fusion
Abstract In the paper a SOLPS-ITER modeling of H-Mode scenarios with different seed impurity gases (N, Ne, Ar, Kr) is performed for ASDEX Upgrade geometry. These gases are compared from the point of view of their radiation efficiency and compression in the divertor, which is generally understood as the ratio of the divertor to upstream ...
I.Yu. Senichenkov, A.G. Poletaeva, E.G. Kaveeva, I.Yu. Veselova, A.R. Nichik, V.A. Rozhansky   +5 more
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Investigating the influence of divertor baffles on nitrogen-seeded detachment in TCV with SOLPS-ITER simulations and TCV experiments

Nuclear Fusion
Plasma edge simulations with the SOLPS-ITER code are performed to study the influence of divertor baffles on nitrogen-seeded detachment in Tokamak à Configuration Variable (TCV) single-null, L-mode discharges. Scans of nitrogen seeding rate are conducted
G. Sun, H. Reimerdes, C. Theiler, B.P. Duval, M. Carpita, C. Colandrea, R. Ducker, O. Février, S. Gorno, L. Simons, E. Tonello, the EUROfusion Tokamak Exploitation Team, the TCV Team   +12 more
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Application of an automated grid deformation tool for divertor shape optimization in SOLPS‐ITER

Contributions to Plasma Physics
AbstractAn optimized divertor design is crucial to maximize the lifetime of plasma‐facing components and reduce costs of future fusion power plants. Numerical shape optimization could be a powerful tool to obtain improved designs in an automated way.
Van den Kerkhof, Sander, Vervloesem, Nathan, Carli, Stefano, Dekeyser, Wouter   +3 more
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Non-monotonic energy flux density profiles at the ITER divertor entrance

Nuclear Fusion
SOLPS-ITER simulations of the ITER baseline ( Q  = 10) plasma boundary, with tungsten (W) targets and drift terms activated, exhibit a radially localised peak in the energy flux density entering the outer divertor, despite constant anomalous transport ...
D. Moulton, R.A. Pitts, X. Bonnin
doaj   +1 more source

Evaluation of SPARC divertor conditions in H-mode operation using SOLPS-ITER

Nuclear Fusion
Abstract The predicted divertor conditions for the SPARC tokamak are calculated using SOLPS-ITER for a range of scrape-off-layer (SOL) heat flux widths λ q , input powers, and particle fueling locations. Under H-mode scenario conditions with an upstream separatrix density of 1
Jeremy D. Lore, Jae-Sun Park, Thomas Eich, Adam Q. Kuang, Matthew L. Reinke, Sebastian De Pascuale, Bart Lomanowski, Alex Creely, John M. Canik   +8 more
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Simulating the Impact of Baffling on Divertor Performance Using SOLPS-ITER

Strong divertor baffling is a feature expected to have a number of advantages for core-edge integration in tokamaks, yet one which requires much more detailed and extensive study. In this work, the impacts of baffling on a hydrogenic plasma are studied in isolation, through artificial fixed-fraction impurity SOLPS-ITER simulations.
Cowley, Cyd, Moulton, David, Lipschultz, Bruce   +2 more
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A novel understanding of the role of plasma-molecular kinetics on divertor power exhaust

Nuclear Fusion
During detachment, a buffer of neutral atoms and molecules builds up between the target and the ionising plasma. Collisions between the plasma and the molecules play an important role in the detachment process.
N. Osborne, K. Verhaegh, D. Moulton, S. Mijin, H. Reimerdes, P. Ryan, N. Lonigro, R. Osawa, K. Murray, S. Kobussen, Y. Damizia, A. Perek, C. Theiler, R. Ducker, D. Mykytchuk, the Eurofusion Tokamak Exploitation Team, the MAST-U Team, the TCV Team   +17 more
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Impact of gas injection location and divertor surface material on ITER fusion power operation phase divertor performance assessed with SOLPS-ITER

Nuclear Fusion
The ITER divertor design and performance assessment, primarily based on the SOLPS-4.3 burning plasma database (Pitts R. et al 2019 Nucl. Mater. Energy   20 100696), assumes the use of beryllium (Be) as the divertor surface material and the injection of ...
Jae-Sun Park, Xavier Bonnin, Richard Pitts, Jeremy Lore   +3 more
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Taming harmful bursts and heat flux in high-confinement tokamak plasmas. [PDF]

Nat Commun
Hu QM, Wang HQ, Navarro M, Wang HH, Eldon D, Gu S, Ma XX, Frerichs H, Scotti F, Wang L, Wilcox RS, Wilks TM, Bortolon A, Ceelen L, Effenberg F, Gong XZ, Jia MN, Kim SK, Lasnier CJ, Leonard AW, Li KD, Logan NC, Ma Q, Maingi R, Meng LY, Moser AL, Osborne TH, Paz-Soldan C, Shafer MW, Sun YW, Yang SM, Ye C.   +31 more
europepmc   +1 more source