Use of Helical Fields to Allow a Long Pulse Reversed Field Pinch

Boozer, Allen H.; Pomphrey, N.

doi:10.2172/941503

Cited by 1 publication

(1 citation statement)

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“…To this end the code had to be modified in order to correctly deal with the RFP toroidal field reversal: the toroidal flux is non-monotonic and cannot be used as a flux surface label as is customary when dealing with the tokamak and stellarator configurations. The code is run providing as input data global plasma quantities such as plasma current, total toroidal flux, q and pressure profiles, as well as a helical axis guess [PB09] (inferred from experimental measurements such as T e profile or SXR tomographic reconstruction). The solution is then determined in a fixed-boundary mode, i.e.…”

Section: Rfp Helical Equilibrium Reconstructionmentioning

confidence: 99%

A 3D approach to equilibrium, stability and transport studies in RFX-mod improved regimes

Terranova

Bonfiglio

Boozer

et al. 2010

Plasma Phys. Control. Fusion

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The full three-dimensional (3D) approach is now becoming an important issue for all magnetic confinement configurations. It is a necessary condition for the stellarator but also the tokamak and the reversed field pinch (RFP) now cannot be completely described in an axisymmetric framework. For the RFP the observation of self-sustained helical configurations with improved plasma performances require a better description in order to assess a new view on this configuration. In this new framework plasma configuration studies for RFX-mod have been considered both with tools developed for the RFP as well as considering codes originally developed for the stellarator and adapted to the RFP. These helical states are reached through a transition to a very low/reversed shear configuration leading to internal electron transport barriers. These states are interrupted by MHD reconnection events and the large T e gradients at the barriers indicate that both current and pressure driven modes are to be considered. Furthermore the typically flat T e profiles in the helical core have raised the issue of the role of electrostatic and electromagnetic turbulence in these reduced chaos regions, so that a stability analysis in the correct 3D geometry is required to address an optimization of the plasma setup. In this view the VMEC code proved to be an effective way to obtain helical equilibria to be studied in terms of stability and transport with a suite of well tested codes. In this work, the equilibrium reconstruction technique as well as the experimental evidence of 3D effects and their first interpretation in terms of stability and transport are presented using both RFP and stellarator tools.

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Section: Rfp Helical Equilibrium Reconstructionmentioning

confidence: 99%