The core of high-beta hybrid tokamaks is sensitive to 3D fields, due to the response of a marginally-stable kink with large m=1/n=1 component as the minimum safety factor approaches unity. Helical core displacements of 1-2cm impact various quantities, as found in ASDEX Upgrade by probing the plasma with n=1 fields: central electron and ion temperature is reduced, causing confinement degradation; core rotation is braked, leading to performance-limiting 2/1 modes as rotation is roughly halved; outward W transport occurs, a potentially beneficial effect. Due to n=1 field amplification, these effects are largest near beta limits and error field correction is applied to minimize them. A modelling effort is ongoing to explain these results. Rotation braking is compared to neoclassical toroidal viscosity predicted by the MHD-kinetic hybrid code MARS-K. The drift-kinetic code NEO-2 is used to evaluate both NTV and the neoclassical W transport in the helical core, represented by a 3D equilibrium from V3FIT-VMEC.

Effects of external 3D fields on the core of high-beta hybrid tokamak plasmas

Piovesan P;Marrelli L;Terranova D;
2017

Abstract

The core of high-beta hybrid tokamaks is sensitive to 3D fields, due to the response of a marginally-stable kink with large m=1/n=1 component as the minimum safety factor approaches unity. Helical core displacements of 1-2cm impact various quantities, as found in ASDEX Upgrade by probing the plasma with n=1 fields: central electron and ion temperature is reduced, causing confinement degradation; core rotation is braked, leading to performance-limiting 2/1 modes as rotation is roughly halved; outward W transport occurs, a potentially beneficial effect. Due to n=1 field amplification, these effects are largest near beta limits and error field correction is applied to minimize them. A modelling effort is ongoing to explain these results. Rotation braking is compared to neoclassical toroidal viscosity predicted by the MHD-kinetic hybrid code MARS-K. The drift-kinetic code NEO-2 is used to evaluate both NTV and the neoclassical W transport in the helical core, represented by a 3D equilibrium from V3FIT-VMEC.
2017
Istituto gas ionizzati - IGI - Sede Padova
external 3D fields
high-beta hybrid tokamak plasma
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.14243/340398
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