Heat and particle transport simulation in COMPASS and T-10 tokamaks with the canonical profile transport model

Мұқаба

Дәйексөз келтіру

Толық мәтін

Аннотация

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.

Авторлар туралы

A. Danilov

National Research Centre “Kurchatov Institute”

Email: danilov_AV@nrcki.ru
Ресей, Moscow, 123182

Yu. Dnestrovskij

National Research Centre “Kurchatov Institute”

Email: nrcki@nrcki.ru
Ресей, Moscow, 123182

A. Melnikov

National Research Centre “Kurchatov Institute”; National Research Nuclear University MEPHI; Moscow Institute of Physics and Technology

Email: nrcki@nrcki.ru
Ресей, Moscow, 123182; Moscow, 115409; Dolgoprudny, 141701

L. Eliseev

National Research Centre “Kurchatov Institute”

Email: nrcki@nrcki.ru
Ресей, Moscow, 123182

S. Lysenko

National Research Centre “Kurchatov Institute”

Хат алмасуға жауапты Автор.
Email: lysenko_SE@nrcki.ru
Ресей, Moscow, 123182

S. Cherkasov

National Research Centre “Kurchatov Institute”

Email: nrcki@nrcki.ru
Ресей, Moscow, 123182

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