Heat and Particle Transport Simulation in COMPASS and T-10 Tokamaks with the Canonical Profile Transport Model

The results of heat and particle transport simulations for ohmic plasma in the T-10 tokamak with a circular limiter and for D-shaped plasma in the COMPASS tokamak with a divertor are presented. In addition, the H-mode with ohmic heating and with additional heating by the neutral beam injection (NBI) in the COMPASS was simulated. The simulations were carried out with the Canonical profile transport model (CPTM) using the ASTRA code. The obtained electron temperature and density profiles agree with the measured ones with standard deviations within the experimental accuracy of 10–15%. The calculations demonstrated very similar density profiles in the H-mode both with the ohmic and with additional NBI heating. The electron temperature profiles in the H-mode with additional heating have higher pedestals than in the ohmic H-mode, that agree with the measurements. The comparison showed that the ohmic regimes in COMPASS and T-10 can be described by the same stiffness coefficients in the heat and particle transport equations.

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Publication Details

Journal
Plasma Physics Reports
Published
2024-12-01
DOI
https://doi.org/10.1134/s1063780x24601780
Primary Topic
Magnetic confinement fusion research
Type
article
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article

Heat and Particle Transport Simulation in COMPASS and T-10 Tokamaks with the Canonical Profile Transport Model

А. В. Данилов, Yu. N. Dnestrovskij, L.G. Eliseev, S. E. Lysenko et al.
Plasma Physics Reports
Magnetic confinement fusion research
article

Heat and Particle Transport Simulation in COMPASS and T-10 Tokamaks with the Canonical Profile Transport Model

А. В. Данилов, Yu. N. Dnestrovskij, L.G. Eliseev, S. E. Lysenko, A. V. Melnikov, С. В. Черкасов
article en

Abstract

The results of heat and particle transport simulations for ohmic plasma in the T-10 tokamak with a circular limiter and for D-shaped plasma in the COMPASS tokamak with a divertor are presented. In addition, the H-mode with ohmic heating and with additional heating by the neutral beam injection (NBI) in the COMPASS was simulated. The simulations were carried out with the Canonical profile transport model (CPTM) using the ASTRA code. The obtained electron temperature and density profiles agree with the measured ones with standard deviations within the experimental accuracy of 10–15%. The calculations demonstrated very similar density profiles in the H-mode both with the ohmic and with additional NBI heating. The electron temperature profiles in the H-mode with additional heating have higher pedestals than in the ohmic H-mode, that agree with the measurements. The comparison showed that the ohmic regimes in COMPASS and T-10 can be described by the same stiffness coefficients in the heat and particle transport equations.

Plasma Physics ReportsVol. 50(12)
Moscow Institute of Physics and Technology (RU), Kurchatov Institute (RU), National Research Nuclear University MEPhI (RU)
Affordable and clean energy
Openalex Percentile: Top 93%
Magnetic confinement fusion research
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Heat and Particle Transport Simulation in COMPASS and T-10 Tokamaks with the Canonical Profile Transport Model — А. В. Данилов, Yu. N. Dnestrovskij, et al. · Plasma Physics Reports (2024) | TGRS Research Map | TGRS