F. Gnesotto
A5091020351- Magnetic confinement fusion research
- Particle accelerators and beam dynamics
- Superconducting Materials and Applications
- Plasma Diagnostics and Applications
- Ionosphere and magnetosphere dynamics
- Fusion materials and technologies
- Particle Accelerators and Free-Electron Lasers
- Electromagnetic Launch and Propulsion Technology
- Solar and Space Plasma Dynamics
- Graphite, nuclear technology, radiation studies
- Laser-Plasma Interactions and Diagnostics
- Engineering and Material Science Research
- Electric Motor Design and Analysis
- Plasma and Flow Control in Aerodynamics
- Muon and positron interactions and applications
- Nuclear Physics and Applications
- Korean Peninsula Historical and Political Studies
- Metallurgical and Alloy Processes
- Sensor Technology and Measurement Systems
- Spacecraft Design and Technology
- Nuclear and radioactivity studies
- Modeling and Simulation Systems
- Non-Destructive Testing Techniques
- Magnetic Field Sensors Techniques
- Power Systems and Technologies
University of Padua
1991-2023
National Agency for New Technologies, Energy and Sustainable Economic Development
2003-2021
National Academies of Sciences, Engineering, and Medicine
2004
Institute of Ionized Gas
1976-1995
Istituto Nazionale di Fisica Nucleare, Sezione di Padova
1993
The ITER Neutral Beam Test Facility (NBTF), called PRIMA (Padova Research on Megavolt Accelerator), is hosted in Padova, Italy and includes two experiments: MITICA, the full-scale prototype of heating neutral beam injector, SPIDER, full-size radio frequency negative-ions source. NBTF realization exploitation SPIDER MITICA have been recognized as necessary to make future operation injectors efficient reliable, fundamental achievement thermonuclear-relevant plasma parameters ITER. This paper...
The ITER project requires additional heating by two neutral beam injectors, each accelerating to 1 MV a 40 A of negative deuterium ions, deliver the plasma power about 17 MW for one hour. As these requirements have never been experimentally met, it was recognized as necessary setup test facility, PRIMA (Padova Research on Megavolt Accelerator), in Italy, including full-size ion source, SPIDER, and prototype whole injector, MITICA, aiming develop injectors be installed ITER. This realization...
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...
FAST is a new machine proposed to support ITER experimental exploitation as well anticipate DEMO relevant physics and technology. aimed at studying, under burning plasma conditions, fast particle (FP) physics, operations wall interaction in an integrated way. has the capability approach all scenarios significantly closer than present day experiments using deuterium plasmas. The necessity of achieving performance with moderate cost led conceiving compact tokamak (R = 1.82m, 0.64m) high...
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...
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...
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...
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...
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...
The RFX-mod device is operated both as a reversed field pinch (RFP), where advanced regimes featuring helical shape develop, and tokamak. Due to its flexibility, contributing the solution of key issues in roadmap ITER DEMO, including MHD instability control, internal transport barriers, edge turbulence, isotopic effect, high density limit three-dimensional (3D) non-linear modelling. This paper reports recent advancements understanding self-organized states, strong electron barrier, RFP...
This paper reports the highlights of RFX-mod fusion science programme since last 2010 IAEA Fusion Energy Conference. The focused on two main goals: exploring potential reversed field pinch (RFP) magnetic configuration and contributing to solution key technology problems in roadmap ITER. Active control several plasma parameters has been a tool this endeavour. New upgrades system for active magnetohydrodynamic (MHD) stability are underway will be presented paper. Unique among existing devices,...
In June 2018 the SPIDER device, which is full-size prototype of negative ion source and extractor for ITER Heating Neutral Beam has entered first operation phase at Test Facility (NBTF) in Padova, Italy. This paper describes present status experimental plans results obtained during campaign radio-frequency driven plasma source.
In this paper, we analyse the main features of pulsed poloidal current drive (PPCD) technique, used in reversed field pinch configuration to achieve improved confinement conditions. RFX experiment, PPCD corresponds a decrease magnetic fluctuations, peaking temperature profile, and reduced transport plasma–wall interaction. A three-dimensional MHD nonlinear code one-dimensional time-dependent models have been applied study effect on plasma profiles. The simulations show that external...
The reversed field pinch (RFP) is a magnetic configuration alternative to the tokamak that can be considered for second generation of reactors. In this paper new remarkable results obtained in RFP experiment RFX-mod are presented, showing an internal transport barrier delimitates large fraction plasma volume when current raised ∼1.5 MA. formation related profound, spontaneous modification topology. Due occurrence saddle node bifurcation enters single helical axis state, which theoretically...