A5061974651- Magnetic confinement fusion research
- Superconducting Materials and Applications
- Particle accelerators and beam dynamics
- Fusion materials and technologies
- Plasma Diagnostics and Applications
- Ionosphere and magnetosphere dynamics
- Gas Dynamics and Kinetic Theory
- Laser-Plasma Interactions and Diagnostics
- Electromagnetic Simulation and Numerical Methods
- Magnetic Field Sensors Techniques
- Non-Destructive Testing Techniques
- Nuclear reactor physics and engineering
- Transplantation: Methods and Outcomes
- Pulsars and Gravitational Waves Research
- Differential Equations and Numerical Methods
- Laser-induced spectroscopy and plasma
- Numerical methods in engineering
- Target Tracking and Data Fusion in Sensor Networks
- Computational Fluid Dynamics and Aerodynamics
- Induction Heating and Inverter Technology
- Advanced Numerical Methods in Computational Mathematics
- Viral Infections and Immunology Research
- Metallurgical Processes and Thermodynamics
- Experimental and Theoretical Physics Studies
- Electromagnetic Scattering and Analysis
National Agency for New Technologies, Energy and Sustainable Economic Development
2019-2024
University of Padua
2019-2024
Culham Centre for Fusion Energy
2024
Università degli studi di Cassino e del Lazio Meridionale
2015-2018
Abstract In 2021 JET exploited its unique capabilities to operate with T and D–T fuel an ITER-like Be/W wall (JET-ILW). This second major campaign (DTE2), after DTE1 in 1997, represented the culmination of a series enhancements—new fusion diagnostics, new injection capabilities, refurbishment plant, increased auxiliary heating, in-vessel calibration 14 MeV neutron yield monitors—as well as significant advances plasma theory modelling community. DTE2 was complemented by sequence isotope...
Abstract An overview is presented of the progress since 2021 in construction and scientific programme preparation Divertor Tokamak Test (DTT) facility. Licensing for building has been granted at end 2021. Cat. A radiologic source also 2022. The toroidal field magnet system progressing. prototype 170 GHz gyrotron produced it now under test on FALCON design vacuum vessel, poloidal coils civil infrastructures completed. shape first DTT divertor agreed with EUROfusion to different plasma exhaust...
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.
Abstract Within the 9th European Framework programme, since 2021 EUROfusion is operating five tokamaks under auspices of a single Task Force called ‘Tokamak Exploitation’. The goal to benefit from complementary capabilities each machine in coordinated way and help developing scientific output scalable future largre machines. programme this ensures that ASDEX Upgrade, MAST-U, TCV, WEST JET (since 2022) work together achieve objectives Missions 1 2 Roadmap: i) demonstrate plasma scenarios...
The dynamics of turbulent filaments in L and ELM-free H-mode the RFX-mod device operating as a tokamak is discussed present work. L-H transition sustained have been achieved with aid an external electrode biasing (Spolaore et al 2017 Nucl. Fusion 57 116039). Through advanced statistical techniques, are detected tracked from edge to scrape-off layer (SOL) two-dimension floating potential map (measured 2D array Langmuir probes) related extreme events fixed ion saturation current signal SOL....
In this paper, DEMO-like shaped plasma equilibria are defined for RFX-mod2 tokamak operations by using the Inverse Equilibrium Tool (IET code). IET allows computation of coil currents needed to obtain a predetermined shape with well global parameters (i.e. total current and poloidal magnetic flux at boundary) solving constrained minimization problem. The new conditions would allow achieving higher density values same toroidal field safety factor limits previous RFX-mod operations....
Abstract RFX-mod2 ( R = 2.0 m, a 0.49 m), the upgraded version of previous RFXmod fusion device, will be equipped with new reflectometry system specifically designed for plasma position control purposes. Featuring high temporal and spatial resolution being suitable harsh reactor experimental conditions (long pulses, neutron fluxes), has been proposed as good candidate this task. On diagnostic consist four bistatic ultrafast independent reflectometric units working in frequency range (16–26.5...
The achievement of new operational conditions in the RFX-mod-shaped tokamak allowed for investigation n = 0 stability and its relationship with a plasma shape cross-section. For this purpose, response models have been produced from CREATE-L code equilibrium reconstructions based on experimental data, their properties related to studied detail. In particular, we find that pure proportional controller is unable stabilize mode all shots due peculiar property are non-minimum phase systems. This...
In this paper we present a coupled Finite Element Method -Boundary (FEM-BEM) approach for the solution of free-boundary axi-symmetric plasma equilibrium problem.The proposed method, obtained from an improvement Hagenow-Lackner coupling allows to efficiently model problem in unbounded domains by discretizing only region; external conductors can be modelled either as 2D or 3D models, according interest.The explores different iterative methods nonlinear Grad-Shafranov equation, such Picard,...
During its experimental campaign, the RFX-mod2 device, upgrade of RFX-mod which is currently in manufacturing phase, expected to explore both Reverse Field Pinch (RFP) and tokamak operations. Both cases will be characterized by strong halo currents, flow from plasma graphite tiles [i.e., facing components (PFCs)], into resistive Inconel 625 cage placed around passive stabilizing Shell (PSS). In order measure such characterize their poloidal distribution, a set Halo Sensors (HSs) installed on...
Abstract In this paper we present a method to compute spatial and time evolution of electromagnetic forces in magnetic confinement fusion devices based on combination signal analysis measurements with simple modelling. The allows analyzing the whole plasma discharge including fast transient phenomena such as terminations or disruptions. It has been tested verified RFX-mod, an experiment equipped non-continuous toroidal passive stabilizing shell, but it can be applied cases continuous wall...
Abstract We present a comparative analysis of practically achievable positive and negative triangularity configurations in the next RFX-mod2 tokamak campaign. The designed single-null plasmas—based on analogous, formerly realized scenarios RFX-mod—are mirrored, keeping most other parameters fixed. In this procedure, we show how some local global geometric properties plasma are modified, these reflect changes vertical stability, low- n ideal stability electrostatic turbulence level.
This article describes a novel and accurate implementation of finite element method-boundary method (FEM-BEM) coupling based on Argyris (AE), for the <inline-formula xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink"> <tex-math notation="LaTeX">$C^{1}$ </tex-math></inline-formula> solution axi-symmetric magnetostatic problems in open boundary domains. The aim work is twofold: 1) to provide novel, easy, way compute basis functions that strongly not...
A meaningful characterization of the magnetic configuration toroidal plasmas requires identification and estimation sources error on each measurement overall diagnostic system. Thus, correct pick-up coil sensors assessment their reliability becomes a necessary requirement before permanent installation in RFX-mod2 experiment. The experimental methodology developed for three-axes experiment is presented here. sensitivity sensor evaluated not only by performing accurate measurements effective...
Abstract The RFX-mod2 device, the upgraded version of previous RFX-mod with a modified magnetic boundary, is presently under realization and will start to be operated in 2025. Significant upgrades diagnostic capabilities have been proposed are development. These include largely increased number in-vessel electrostatic sensors, new fast reciprocating manipulator for exploration edge plasma wide range experimental conditions, improved Thomson scattering soft x-ray diagnostics system detailed...
Abstract The external kink related sideways wall force is investigated on ultralow-q&#xD;RFX-mod plasma discharge. Several theoretical predictions are experimentally&#xD;verified. presence of coupled modes observed when the subject&#xD;to a force. absence an integral electromagnetic is&#xD;analyzed in such conditions. dependence mode growth&#xD;rate also revealed. A comparison between different the&#xD;sideways magnitude performed for both flat-top and ramp-down...
Abstract A low-temperature plasma can very well be confined by a simple magnetic dipole, such as in the Van Allen belts of Earth’s magnetoshpere. This configuration reproduced laboratory small experimental device, designed way that field lines remain within vacuum-tight container and are virtually not intercepted wall. In this paper we propose to use dipole for realization an efficient negative Ion source. To purpose, analyze confinement capabilities source, order assess equilibrium pressure...