A 3D approach to equilibrium, stability and transport studies in RFX-mod improved regimes
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Transport phenomena in tokamak plasmas strongly limit the particle and energy confinement and represent a crucial obstacle to controlled thermonuclear fusion. Within the vast framework of transport studies, three topics have been tackled in the present the ...
Stability results for high-n ideal local pressure-driven instabilities (ballooning and interchange: modes) are calculated from the COBRA and TERPSICHORE codes and compared for several low aspect ratio stellarators. Such a comparison is important because of ...
First global linear study of electrostatic drift waves in two realistic quasisymmetric configurations, namely the Quasi-Axially symmetric Stellarator with three fields periods (QAS3) [P. Garabian and L. P. Ku, Phys. Plasma 6, 645 (1999)] and the Helically ...
Strategies for the improvement of quasiaxisymmetric stellarator configurations are explored. Calculations of equilibrium flux surfaces for candidate configurations are also presented. One optimization strategy is found to generate configurations with impro ...
The influence of shaping and toroidicity on the ideal MHD stability of the reversed field pinch (RFP) is investigated with respect to current driven and pressure driven modes. It is found that triangularity and X-point shaping does not significantly modify ...
A modified CPG in the high density regime of 20-70mT of He was investigated. The injection of the plasmatorus into a driftspace was studied by diamagnetical diagnostics both with and without helical bias, where the inner electrode was continued into the dr ...
Recent stability results of external kink modes and vertical modes in compact stellarators are presented. The vertical mode is found to be stabilized by externally generated poloidal flux. A simple stability criterion is derived in the limit of large aspec ...
A particular configuration of the LHD stellarator with an unusually flat pressure profile has been chosen to be a test case for comparison of the MHD stability property predictions of different three-dimensional and averaged codes for the purpose of code c ...
The TCV tokamak has 16 poloidal field coils for plasma shaping, distributed around the vacuum vessel. Experiments are described that determine the relative merits of different coil positions for controlling the unstable vertical movement of elongated plasm ...