Control of non-axisymmetric magnetic fields for plasma enhanced performances: The RFX contribution

Sonato, P.; Piovan, R.; Luchetta, A.

doi:10.1016/j.fusengdes.2005.08.009

Cited by 13 publications

(11 citation statements)

References 32 publications

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“…25 While RFX-mod plasma discharges have been performed mainly in the reversed field pinch (RFP) configuration, recent developments allow now operating the device also with magnetic geometries that feature inner-wall limited and diverted ohmic tokamaks. 26,28,29 Using a toroidal magnetic field on axis B u ' 0:6 T and a plasma current up to I p ' 150 kA, it is possible to perform plasma pulses longer than 1 s with integrated plasma densities n e !…”

Section: The Experimental Setupmentioning

confidence: 99%

“…More precisely, we investigate the SOL plasma dynamics in a circular limiter configuration with a low safety factor at the last close flux surface (LCFS), q LCFS Շ3, for which the SOL turbulence is expected to be clearly in the inertial DW (InDW) regime. 12 Our study is based on performing SOL turbulence simulations considering two tokamak circular plasma discharges carried out in the RFX-mod experiment 25 with q LCFS % 2, 3. The RFX-mod device can access such low safety factors thanks to an advanced feedback magnetic boundary control a) Electronic mail: fabio.riva@ukaea.uk system, which allows stabilizing resistive wall modes and performing plasma discharges with q LCFS % 2 without disruptions.…”

Section: Introductionmentioning

confidence: 99%

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Three-dimensional simulations of plasma turbulence in the RFX-mod scrape-off layer and comparison with experimental measurements

et al. 2018

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The tokamak scrape-off layer (SOL) plasma dynamics is investigated in a circular limiter configuration with a low edge safety factor. Focusing on the experimental parameters of two ohmic tokamak inner-wall limited plasma discharges in RFX-mod [Sonato et al., Fusion Eng. Des. 74, 97 (2005)], nonlinear SOL plasma simulations are performed with the GBS code [Ricci et al., Plasma Phys. Controlled Fusion 54, 124047 (2012)]. The numerical results are compared with the experimental measurements, assessing the reliability of the GBS model in describing the RFX-mod SOL plasma dynamics. It is found that the simulations are able to quantitatively reproduce the RFX-mod experimental measurements of the electron plasma density, electron temperature, and ion saturation current density (jsat) equilibrium profiles. Moreover, there are indications that the turbulent transport is driven by the same instability in the simulations and in the experiment, with coherent structures having similar statistical properties. On the other hand, it is found that the simulation results are not able to correctly reproduce the floating potential equilibrium profile and the jsat fluctuation level. It is likely that these discrepancies are, at least in part, related to simulating only the tokamak SOL region, without including the plasma dynamics inside the last close flux surface, and to the limits of applicability of the drift approximation. The turbulence drive is then identified from the nonlinear simulations and with the linear theory. It results that the inertial drift wave is the instability driving most of the turbulent transport in the considered discharges.

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Section: The Experimental Setupmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Three-dimensional simulations of plasma turbulence in the RFX-mod scrape-off layer and comparison with experimental measurements

et al. 2018

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“…RFX-mod addresses the control of MHD modes by acting on the magnetic configuration at the plasma boundary [6]. This corresponds to the concept of a discrete active shell as proposed for the first time in late 1980s [7].…”

Section: Introductionmentioning

confidence: 99%

Feedback control of resistive wall modes by saddle coils in RFX-mod

Bolzonella

Cavinato

Gaio

et al. 2007

Fusion Engineering and Design

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“…In the frequency range I f the compensated plant has the property that if the reference signals satisfy condition (1), that is to say they are admissible, they are presented at the output ports of the plant unchanged. Thus, in the space of the admissible inputs, the compensated plant is the identity, at least for those inputs with limited band.…”

Section: Controller Synthesismentioning

confidence: 99%

“…Experiments in the RFP configuration may play an important role in this framework: due to the richer harmonic content of the edge magnetic field perturbations compared to the Tokamak, the RFP is a challenging test-bed for the development of edge magnetic field control scenarios. RFX-mod [1] has been designed with the aim of extensive experimental activity in this field, its toroidal surface being completely covered with 192 saddle coils independently fed and 192 × 3 underlying sensors for the measure of the radial, toroidal and poloidal components of the magnetic field. Different control strategies acting either equally on all the radial magnetic field harmonic components (virtual shell) or selectively on subsets of them (mode control) have been implemented.…”

Section: Introductionmentioning

confidence: 99%