Design and operation of the RFX-mod plasma shape control system

Marchiori, G.; Finotti, Claudio; Kudláček, O.; Villone, F.; Zanca, P.; Abate, Domenico; Cavazzana, R.; Jackson, G.L.; Luce, T. C.; Marrelli, L.

doi:10.1016/j.fusengdes.2016.04.042

Cited by 17 publications

(21 citation statements)

References 19 publications

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“…Considering the presence of 28 tiles, an array of 12 (toroidal) x 14 (poloidal) sensors is foreseen as the minimum requirement for a measurementbased and reliable equilibrium reconstruction. This magnetic diagnostic improvement will allow a strong enhancement in the control of magnetic equilibrium and plasma shape, thus increasing the flexibility in the position of the Xpoint [82,83]; also negative triangularity shaping will be tested, as anticipated in section 4. In tokamak configuration, the RFX-mod MHD active control system offers the opportunity for ELM mitigation and edge transport control experiments by means of RMP techniques, easily testing a variety of mode control strategies in H-mode.…”

Section: Proposed Device Upgradesmentioning

confidence: 99%

Overview of the RFX-mod fusion science activity

Zuin¹,

Bello²,

Marrelli³

et al. 2017

Nucl. Fusion

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This paper reports the main recent results of the RFX-mod fusion science activity. The RFX-mod device is characterized by a unique flexibility in terms of accessible magnetic configurations. Axisymmetric and helically shaped Reversed-field pinch equilibria have been studied, along with tokamak plasmas in a wide range of q(a) regimes (spanning from 4 down to 1.2 values). The full range of magnetic configurations in between the two, the so-called ultra low-q ones, has been explored, with the aim of studying specific physical issues common to all equilibria, such as, for example, the density limit phenomenon. The powerful RFX-mod feedback control system has been exploited for MHD control, which allowed to extend the range of experimental parameters, as well as to induce specific magnetic perturbations for the study of 3D effects. In particular, transport, edge and isotope effect in 3D equilibria have been investigated, along with runaway mitigations through induced magnetic perturbations. The first transitions to an improved confinement scenario in circular and D-shaped tokamak plasmas have been obtained thanks to an active modification of the edge electric field through a polarized electrode. The experiments are supported by intense modelling with 3D MHD, gyrokinetic, guiding center and transport codes. Proposed modifications to the RFX-mod device, which will enable further contributions to the solution of key issues in the roadmap to ITER and DEMO, are also briefly presented.

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Section: Proposed Device Upgradesmentioning

confidence: 99%

Overview of the RFX-mod fusion science activity

Zuin¹,

Bello²,

Marrelli³

et al. 2017

Nucl. Fusion

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“…shot no. 36922) is an Upper Single Null (USN) discharge [24] lasting approximately 1.1s, whose equilibrium at t = 0.6s has been already shown in Fig. 9b.…”

Section: Validation Against Rfx-mod Experimental Datamentioning

confidence: 77%

Efficient Numerical Solution of Coupled Axisymmetric Plasma Equilibrium and Eddy Current Problems

et al. 2023

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This paper presents an efficient numerical tool for solving the problem of transient nonlinear evolution of plasma equilibrium in presence of eddy currents. The code, named FRIDA-TD (FRIDA-Time Domain), and based on the existing FRIDA (FRee-boundary Integro-Differential Axisymmetric) code, exploits two different approaches for solving the elated nonlinear system of Partial Differential Equations (PDE): (i) Finite Element Method -Boundary Element Method (FEM-BEM) for plasma equilibrium, and (ii) Axisymmetric Volume Integral (AVI) formulation for eddy currents. The resulting FRIDA-TD is a fast and flexible tool suitable for engineeringoriented purposes, such as the design of Tokamak devices, set up of plasma operations, prediction of performance scenarios, and design of feedback control systems. FRIDA-TD is successfully validated at first with the well-established CarMa0NL code, and then against experimental data of the RFXmod device.

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“…The vertical stability of the four equilibria is analyzed using the CREATE-L model [20]. In the past, CREATE-L models allowed for a successful full model-based design and testing of RFX-mod plasma vertical stability and shape control systems [21]. Moreover, it allows one to study the macroscopic stability of plasma equilibrium by performing an eigenvalue analysis of the state dynamic matrix of the model: the presence of an unstable mode is revealed by a positive eigenvalue that is representative of the ideal n = 0 mode growth rate.…”

Section: Vertical Stabilitymentioning

confidence: 99%

Positive and negative triangularity in RFX-mod2: a comparative analysis

Predebon¹,

Abate²,

Pigatto³

2022

Nucl. Fusion

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We present a comparative analysis of practically achievable positive and negative triangularity configurations in the next RFX-mod2 tokamak campaign. The designed single-null positive triangularity plasmas -- based on analogous, formerly realized scenarios in RFX-mod -- are mirrored keeping most of the other parameters fixed. In this procedure, we show how some local and global geometric properties of the plasma are modified, and how these properties reflect on changes in vertical stability, low-n ideal stability, and electrostatic turbulence level.

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Design and operation of the RFX-mod plasma shape control system

Cited by 17 publications

References 19 publications

Overview of the RFX-mod fusion science activity

Overview of the RFX-mod fusion science activity

Efficient Numerical Solution of Coupled Axisymmetric Plasma Equilibrium and Eddy Current Problems

Positive and negative triangularity in RFX-mod2: a comparative analysis

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