G. Marchiori
A5045489655- Magnetic confinement fusion research
- Superconducting Materials and Applications
- Particle accelerators and beam dynamics
- Ionosphere and magnetosphere dynamics
- Plasma Diagnostics and Applications
- Fusion materials and technologies
- Laser-Plasma Interactions and Diagnostics
- Magnetic Field Sensors Techniques
- Electromagnetic Launch and Propulsion Technology
- Particle Accelerators and Free-Electron Lasers
- Plasma and Flow Control in Aerodynamics
- Geophysical Methods and Applications
- Magnetic Properties and Applications
- Solar and Space Plasma Dynamics
- Atomic and Subatomic Physics Research
- Nuclear reactor physics and engineering
- Nuclear Physics and Applications
- Non-Destructive Testing Techniques
- Electromagnetic Simulation and Numerical Methods
- Quantum chaos and dynamical systems
- Induction Heating and Inverter Technology
- Control Systems and Identification
- CCD and CMOS Imaging Sensors
- Radiation Effects in Electronics
- Space Satellite Systems and Control
National Agency for New Technologies, Energy and Sustainable Economic Development
2014-2024
Institute for the Science and Technology of Plasmas
2022-2024
University of Padua
1995-2023
Institute of Plasma Physics
2019
Innova (Italy)
2019
Centro Ricerche FIAT
2018
Institute of Ionized Gas
1989-2013
Istituto Nazionale di Fisica Nucleare, Sezione di Padova
1993-2002
The plasma diagnostic and control (D&C) system for a future tokamak demonstration fusion reactor (DEMO) will have to provide reliable operation near technical physics limits, while its front-end components be subject strong adverse effects within the nuclear high temperature environment. ongoing developments ITER D&C represent an important starting point progressing towards DEMO. Requirements detailed exploration of are however pushing design using sophisticated methods aiming large spatial...
Heating neutral beam (HNB) injectors, necessary to achieve burning conditions and control plasma instabilities in ITER, are characterized by such demanding parameters that a test facility (NBTF) dedicated their development optimization is being realized Padua (Italy) with direct contributions from the Italian government (through Consorzio RFX as host entity) ITER international organization (with kind domestic agencies of Europe, Japan India) technical scientific support various European...
The requirements of ITER neutral beam injectors (1 MeV, 40 A negative deuterium ion current for 1 h) have never been simultaneously attained; therefore, a dedicated Neutral Beam Test Facility (NBTF) was set up at Consorzio RFX (Padova, Italy). NBTF includes two experiments: SPIDER (Source the Production Ions Deuterium Extracted from Rf plasma), full-scale prototype source injectors, with 100 keV accelerator, to investigate and optimize properties source; MITICA, entire injector, devoted...
An initial concept for the plasma diagnostic and control (D&C) system has been developed as part of European studies towards development a demonstration tokamak fusion reactor (DEMO). The main objective is to develop feasible, integrated design DEMO D&C that can provide reliable high performance (electricity output) over extended periods operation. While power maximized when operating near operational limits tokamak, reliability operation typically improves choosing parameters significantly...
Stable operation with control on magnetohydrodynamic modes has been obtained in the modified reversed field experiment employing a set of 192 feedback controlled saddle coils. Improvements plasma temperature, confinement (twofold), and pulse length (threefold) and, as consequence magnetic fluctuation reduction, strong mitigation plasma-wall interaction mode locking are reported.Received 27 January 2006DOI:https://doi.org/10.1103/PhysRevLett.97.075001©2006 American Physical Society
Due to their discrete nature, a grid of active coils for the feedback control plasma instabilities produces an infinite sequence sideband harmonics in magnetic field. If sensors have same periodicity as coils, intelligent shell scheme (Bishop 1989 Plasma Phys. Control. Fusion 31 1179), aliasing sidebands determines systematic error on Fourier analysis measurements. Since relies raw measurements, it does not recognize effect. This is drawback field compensation and those perturbations that...
RFX-mod is a Reversed Field Pinch device that allowed performing experiments in regimes with plasma current up to 2 MA, thanks its MHD active control system. Experiments have shown improved performances are obtained when the resonant part of m = 1 spectrum one dominant tearing mode much higher than other secondary ones (quasi single helicity states). Tearing modes play crucial role determining energy and particle transport. Based on present understanding interplay between passive conductive...
Active feedback stabilization of multiple independent resistive wall modes is experimentally demonstrated in a reversed-field pinch plasma. A reproducible simultaneous suppression several nonresonant achieved. Coupling different due to the limited number coils observed agreement with theory. The RWMs also has an effect on tearing that are resonant central plasma, leading significant prolongation discharge pulse.
Two issues of the resistive wall mode (RWM) control code maturity are addressed: inclusion advanced damping physics beyond ideal MHD description, and possibility taking into account influence 3D features conducting structures on stability control. Examples formulations computational results given, using MARS-F/K codes CarMa code. The MARS-K calculations for a DIII-D plasma shows that fast ion contributions, which can give additional drift kinetic stabilization in perturbative approach, also...
RFX-mod is a reversed field pinch (RFP) experiment equipped with system that actively controls the magnetic boundary. In this paper we describe results of new control algorithm, clean mode (CMC), in which aliasing sideband harmonics generated by discrete saddle coils corrected real time. CMC operation leads to smoother (i.e. more axisymmetric) Tearing modes rotate (up 100 Hz) and partially unlock. Plasma–wall interaction diminishes due decrease non-axisymmetric shift plasma column. With...
With the exploration of MA plasma current regime in up to 0.5 s long discharges, RFX-mod has opened new and very promising perspectives for reversed field pinch (RFP) magnetic configuration, made significant progress understanding improving confinement controlling stability. A big leap with respect previous knowledge expectations on RFP physics performance been by since last 2006 IAEA Fusion Energy Conference. self-organized helical equilibrium experimentally achieved (the Single Helical...
Abstract The RFX-mod2 installation is planned to be completed by 2024 and the start of operations expected in 2025. high flexibility machine (already tested previous RFX-mod experiment) allows operation Reversed Field Pinch tokamak configuration as well ultra-low q pulses. In this work we present predictive analysis on transport, performances plasma control view first experimental campaigns.
Optimization of machine operation, including plasma position control, density control and especially feedback on multiple magnetohydrodynamic modes, has led RFX-mod to operate reliably at 1.5 MA, the highest current ever achieved a reversed field pinch (RFP). At high low magnetic topology spontaneously self-organizes in an Ohmical helical symmetry, with new axis helically twisting around geometrical torus. The separatrix island disappears leaving wide symmetric thermal structure large...
The reversed field pinch configuration is characterized by the presence of magnetic structures both in core and at edge: core, high plasma current spontaneous development a helical structure accompanied appearance internal electron transport barriers; edge strong pressure gradients, identifying an barrier, are observed too, related to position reversal surface.
This paper reports the main recent results of RFX-mod fusion science activity.The device is characterized by a unique flexibility in terms accessible magnetic configurations.Axisymmetric and helically shaped Reversed-field pinch equilibria have been studied, along with tokamak plasmas wide range q(a) regimes (spanning from 4 down to 1.2 values).The full configurations between two, so-called ultra low-q ones, has explored, aim studying specific physical issues common all equilibria, such as,...
The modified RFX is a very flexible device used for variety of control schemes MHD instabilities and advanced reverse field pinch scenarios. Relative to the previous machine, RFX-mod has thin Cu shell with vertical penetration time τS, lowered from 450 50 ms shell/plasma proximity b/a = 1.24–1.1. Toroidal equilibrium feedback-controlled new power supplies provide better B control. Newly designed graphite tiles protect vessel localized deposition. A mesh 192 external saddle coils, supervised...
The full three-dimensional (3D) approach is now becoming an important issue for all magnetic confinement configurations. It a necessary condition the stellarator but also tokamak and reversed field pinch (RFP) cannot be completely described in axisymmetric framework. For RFP observation of self-sustained helical configurations with improved plasma performances require better description order to assess new view on this configuration. In framework configuration studies RFX-mod have been...
This paper summarizes the main achievements of RFX fusion science program in period between 2008 and 2010 IAEA Fusion Energy Conferences. RFX-mod is largest reversed field pinch world, equipped with a system 192 coils for active control MHD stability. The discovery understanding helical states electron internal transport barriers core temperature >1.5 keV significantly advances perspectives configuration. Optimized experiments plasma current up to 1.8 MA have been realized, confirming...
Abstract In this paper, the results of resistive wall mode (RWM) control experiments using several sets active coils are presented. The effectiveness as a function coil number and covered torus surface is studied in RFX-mod device, thanks to powerful flexible MHD system. Active tried similar size both reversed field pinch (RFP) tokamak configurations, giving good experimental set exploit differences between two cases. compared with predictions by new integrated simulator for closed loop RWM...
Feedback stabilization of the m = 2, n 1 resistive wall mode in q(a) < 2 plasmas is obtained RFX-mod device operated as a circular tokamak. The feedback scheme implements radial sensors within clean control (CMC) algorithm, technique based on de-aliasing measurements from high periodicity sidebands produced by coils. A cylindrical zero-pressure MHD model, which includes realistic discrete-time description feedback, able to explain main features experimental observation, including necessity...
Arrays of magnetic coils and sensors in the EXTRAP T2R [P. R. Brunsell et al., Plasma Phys. Controlled Fusion 43 1457 (2001)] reversed-field pinch have been used to investigate plasma response an applied resonant perturbation range resistive-wall modes (RWMs). Measured RWM growth rates agree with predictions a cylindrical ideal-plasma model. The linear low-n marginally stable RWMs is related so-called resonant-field amplification due dominant ∣n∣=2 machine error field about 2 G. dynamics m=1...