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Start Over Descriptor "TGLF" Topic h-mode
2 results on '"TGLF"'

1. The feasibility of the L-H transition for a purely electron-heated EU-DEMO tokamak

Author

G. Suárez López, G. Tardini, E. Fable, M. Siccinio, and H. Zohm

Subjects
L-H transition, DEMO, ASTRA, TGLF, L-mode, H-mode, Nuclear and particle physics. Atomic energy. Radioactivity, QC770-798
Abstract

We study numerically the feasibility of achieving the L-H transition in the current EU-DEMO tokamak baseline using uniquely direct electron heating. The ASTRA code coupled to the TGLF turbulent transport model is used to predict steady-state kinetic plasma profiles for diverse numerical scans. Among them, we have varied the separatrix electron density, the total amount of ECRH power, the microwave beam deposition profile and the plasma impurity content. The solutions are then compared to L-H transition scaling laws to assess whether the found plasma state would enter into H-mode. We find the plasma density and impurity content to be the key variables setting the boundaries in parameter space where the L-H transition is feasible. When impurities can be controlled under a certain threshold, given here for a fully shaped DEMO plasma, the L-H transition is achieved in all the studied conditions.

Published
2024
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2. H-mode characterisation for dominant ECRH and comparison to dominant NBI or ICRF heating at ASDEX Upgrade.

Author

Sommer, F., Stober, J., Angioni, C., Fable, E., Bernert, M., Burckhart, Bobkov, V., Fischer, R., Fuchs, C., McDermott, R. M., Suttrop, W., and Viezzer, E.

Subjects
*H-mode plasma confinement, *ELECTRON-ion collisions, *HEAT transfer, *ION channels, *ION temperature, *ELECTRON cyclotron resonance heating, *PLASMA heating, *CYCLOTRON resonance
Abstract

At ASDEX Upgrade the ECRH system has been upgraded to provide up to 4 MW of heating power at 140 GHz (or 2:2 MW at 105 GHz). The power at 140 GHz exceeds the minimum H-mode power threshold for typical high Ip; Bt conditions by approximately a factor of two. The upgrade allows H-modes with dominant electron heating and significant electron-ion heat exchange to be studied, i.e. the situation expected in ITER. This paper reports on systematic studies varying the heating mix with NBI, ICRF and ECRH and its effect on pedestal parameters and core transport. The H-mode pedestal is hardly affected by the choice of heating mix, but the ion temperature in the plasma center is found to vary significantly. The ion channel dominates heat transport and ion temperature gradient modes (ITG) are found to be the most unstable microinstability in all the scenarios considered. R/LTi at half radius reduces by a factor of two when Te/Ti increases from 0.9 to 1.5. TGLF modelling of the electron and ion temperature and electron density profiles shows very good agreement with the experimental data when applying a realistic sawtooth model. [ABSTRACT FROM AUTHOR]

Published
2014
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