The role of drifts in the plasma transport at the tokamak core–SOL interface
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference10 articles.
1. Heuristic drift-based model of the power scrape-off width in low-gas-puff H-mode tokamaks
2. Fluid code simulations of radial electric field in the scrape-off layer of JET
3. Theory of plasma transport in toroidal confinement systems
4. Measurement of Natural Plasma Flow along the Field Lines in the Scrape-Off Layer on the JT-60U Divertor Tokamak
5. Classical drifts in the tokamak SOL and divertor: models and experiment
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1. Numerical implications of including drifts in SOLPS-ITER simulations of EAST;Physics of Plasmas;2024-02-01
2. Impurity transport and divertor retention in Ar and N seeded SOLPS 5.0 simulations for ASDEX Upgrade;Plasma Physics and Controlled Fusion;2020-07-14
3. Simulations of divertor heat flux width using transport code with cross-field drifts under the BOUT++ framework;AIP Advances;2020-01-01
4. Drift driven cross-field transport and scrape-off layer width in the limit of low anomalous transport;Plasma Physics and Controlled Fusion;2018-08-23
5. Drifts, currents, and power scrape-off width in SOLPS-ITER modeling of DIII-D;Nuclear Materials and Energy;2017-08
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