F. Villone

ORCID: 0000-0003-4955-7988
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Research Areas
  • Magnetic confinement fusion research
  • Superconducting Materials and Applications
  • Fusion materials and technologies
  • Particle accelerators and beam dynamics
  • Ionosphere and magnetosphere dynamics
  • Electromagnetic Simulation and Numerical Methods
  • Electromagnetic Scattering and Analysis
  • Plasma Diagnostics and Applications
  • Electromagnetic Compatibility and Noise Suppression
  • Non-Destructive Testing Techniques
  • Laser-Plasma Interactions and Diagnostics
  • Nuclear reactor physics and engineering
  • Carbon Nanotubes in Composites
  • Physics of Superconductivity and Magnetism
  • Magnetic Properties and Applications
  • Lightning and Electromagnetic Phenomena
  • Power System Optimization and Stability
  • Graphene research and applications
  • Electromagnetic Compatibility and Measurements
  • Advanced Numerical Methods in Computational Mathematics
  • Advanced Antenna and Metasurface Technologies
  • Numerical methods in engineering
  • Low-power high-performance VLSI design
  • Microwave and Dielectric Measurement Techniques
  • Welding Techniques and Residual Stresses

Università degli studi di Cassino e del Lazio Meridionale
2011-2025

Consorzio CREO (Italy)
2007-2024

University of Naples Federico II
1996-2024

CEA Cadarache
2024

Ingegneria dei Trasporti (Italy)
2003-2024

Culham Science Centre
2008-2024

University of Rome Tor Vergata
2024

Culham Centre for Fusion Energy
2008-2024

Center for Research and Telecommunication Experimentation for Networked Communities
2022-2023

Royal Military Academy
2020

In a power plant scale fusion reactor, huge amount of thermal produced by the reaction and external heating must be exhausted through narrow area divertor targets. The targets withstand intense bombardment diverted particles where high heat fluxes are generated erosion takes place on surface. A considerable volumetric nuclear also exhausted. To cope with such an unprecedented exhaust challenge, highly efficient cooling capacity is required. Furthermore, fulfill other critical functions as...

10.1016/j.fusengdes.2022.113010 article EN cc-by-nc-nd Fusion Engineering and Design 2022-01-13

CREATE-L, a simple and reliable linearized plasma response model for the control of current, position shape in tokamaks, is presented. The basic assumption made that behaviour described using three degrees freedom, related to total internal inductance poloidal beta. state variables are coil currents; inputs applied voltages, whereas beta play role disturbances. outputs field flux values some parameters. tested against non-linear codes validated via comparison with experimental results.

10.1088/0029-5515/38/5/307 article EN Nuclear Fusion 1998-05-01

In the European fusion roadmap, ITER is followed by a demonstration power reactor (DEMO), for which conceptual design under development. This paper reports first results of coherent effort to develop relevant physics knowledge that (DEMO Physics Basis), carried out experts. The program currently includes investigations in areas scenario modeling, transport, MHD, heating & current drive, fast particles, plasma wall interaction and disruptions.

10.1088/0029-5515/55/6/063003 article EN cc-by Nuclear Fusion 2015-04-30

Abstract A large scale program to develop a conceptual design for demonstration fusion power plant (DEMO) has been initiated in Europe. Central elements are the baseline points, which developed by system codes. The assessment of credibility these points is often hampered missing information. main physics and technology content central European codes have published (Kovari et al 2014 Fusion Eng. Des . 89 3054–69, 2016 104 9–20, Reux 2015 Nucl. 55 073011). In addition, this publication...

10.1088/0029-5515/57/1/016011 article EN Nuclear Fusion 2016-10-11

COMPASS Upgrade is a new medium size, high magnetic field tokamak (R = 0.9 m, Bt 5 T, Ip 2 MA) currently under design in the Czech Republic. It will provide unique capabilities for addressing some of key challenges plasma exhaust physics, advanced confinement modes and configurations as well testing facing materials liquid metal divertor concepts. This paper contains an overview preliminary engineering main systems (vacuum vessel, central solenoid poloidal coils, toroidal support structure,...

10.1016/j.fusengdes.2021.112490 article EN cc-by-nc-nd Fusion Engineering and Design 2021-03-23

This work presents an overview of the integrated strategy developed, as part DEMO Key Design Integration Issue 1 (KDII1), to protect EU-DEMO first wall (FW) from planned and unplanned plasma transients by employing discrete limiters. The present Breeding Blanket (BB) FW design, which aims at minimizing loss neutrons while travelling breeding zone, is able withstand steady state heat fluxes up ≈1-1.5 MW/m² [1], not sufficient guarantee its integrity for most plasma-FW direct contact....

10.1016/j.fusengdes.2022.113067 article EN cc-by Fusion Engineering and Design 2022-02-20

An integral formulation to model, in the frequency domain, electromagnetic response of three-dimensional (3-D) structures formed by metallic carbon nanotubes and conductors, within framework classical electrodynamics, is described. The conduction electrons nanotube are modeled as an infinitesimally thin cylindrical layer compressible fluid, whose dynamics described means linearized hydrodynamic equations. resulting equations solved numerically finite element method using facet elements...

10.1109/tap.2006.882170 article EN IEEE Transactions on Antennas and Propagation 2006-10-01

With reference to toroidal fusion devices, we solve axisymmetric nonlinear evolutionary equilibrium equations, describing the plasma behaviour, self-consistently coupled eddy currents surrounding three-dimensional (3D) structures. This formulation allows analysis of quasi-static evolution in presence 3D volumetric conductors. Several validations and test cases are presented, suggesting potential applications proposed method various situations scientific technical interest for future devices...

10.1088/0741-3335/55/9/095008 article EN Plasma Physics and Controlled Fusion 2013-07-16

Heat and particle loads on the plasma facing components are among most challenging issues to be solved for a reactor design. Alternative magnetic configurations may enable tokamak operation with lower peak heat load than standard single null (SN) divertor. This papers reports creation control of one such alternatives: two-null nearby divertor configuration. An important element this study is that was produced large superconducting as an experimental advanced tokamak. A preliminary experiment...

10.1088/0029-5515/55/8/083005 article EN Nuclear Fusion 2015-06-30

Abstract A transmission line (TL) model describing the propagation of electric signals along metallic single wall carbon nanotube (CNT) interconnects is derived in a simple and self‐consistent way within framework classical electrodynamics. The conduction electrons CNTs are modelled as an infinitesimally thin cylindrical layer compressible charged fluid with friction, moving uniform neutralizing background. dynamic electron studied by means linearized hydrodynamic equations pressure assumed...

10.1002/cta.396 article EN International Journal of Circuit Theory and Applications 2006-12-11

In this Letter, the linear stability of resistive wall modes (RWMs) in toroidal geometry for a reversed field pinch (RFP) plasma is studied. Three computational models are used: cylindrical code ETAW, MHD MARS-F, and CarMa code, able to take fully into account effects three-dimensional conducting structure which mimics real shell experimental device. The computed mode growth rates generally agree with data. features shell, like gaps, allow novel interpretation RWM spectrum RFP's remove its...

10.1103/physrevlett.100.255005 article EN Physical Review Letters 2008-06-25

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...

10.1088/0741-3335/52/10/104002 article EN Plasma Physics and Controlled Fusion 2010-09-07

In this paper, a coupling strategy based on the control surface concept is used to self-consistently couple linear MHD solvers 3D codes for eddy current computation of currents in metallic structures surrounding plasma. The performed by assuming that plasma inertia (and, with it, all Alfven wave-like phenomena) can be neglected time scale interest, which dictated relevant electromagnetic structures. As shown, results perturbations inductance matrix operator. particular, adopting Fourier...

10.1088/0741-3335/50/8/085004 article EN Plasma Physics and Controlled Fusion 2008-05-29

In this paper, a new circuit model for the propagation of electric signals along carbon nanotube interconnects is derived from fluid description electrodynamics. The conduction electrons are regarded as 2-D charged fluid, interacting with electromagnetic field produced by ion lattice, electron themselves, and external sources. This interaction may be assumed to governed linearized Euler's equation, which provides constitutive equation coupled Maxwell equations. A derivation then possible...

10.1109/tnano.2008.2010545 article EN IEEE Transactions on Nanotechnology 2008-12-18

Asymmetrical disruptions may occur during ITER operation and they be accompanied by large sideways forces rotation of the asymmetry. This is particular concern because resonance rotating asymmetry with natural frequencies vacuum vessel (and other in-vessel components) could lead to dynamic amplification forces. A significant fraction non-mitigated JET have toroidally asymmetric currents that flow partially inside plasma surrounding ('wall'). The toroidal asymmetries (otherwise known as...

10.1088/0029-5515/55/11/113006 article EN Nuclear Fusion 2015-09-01

Self-consistent computations are carried out to study the stability of resistive wall mode (RWM) in DIII-D [J. L. Luxon, Nucl. Fusion 42, 614 (2002)] plasmas with slow plasma rotation, using hybrid kinetic-magnetohydrodynamic code MARS-K [Y. Q. Liu et al., Phys. Plasmas 15, 112503 (2008)]. Based on kinetic resonances between and thermal particle toroidal precession drifts, self-consistent modeling predicts less stabilization compared perturbative approaches, experiments. A simple analytic...

10.1063/1.3123388 article EN Physics of Plasmas 2009-04-29

This paper addresses the problem of scaling interconnects to nanometric dimensions in future very-large-scale integration applications. Traditional copper are compared innovative made by bundles metallic carbon nanotubes. A new model is presented describe propagation electric signals along nanotube (CNT) bundles, framework classical transmission line theory. possible implementation a scaled microstrip based on CNT bundle analyzed and conventional microstrip.

10.1109/tadvp.2008.2005001 article EN IEEE Transactions on Advanced Packaging 2008-11-01

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...

10.1088/0029-5515/49/10/104019 article EN Nuclear Fusion 2009-09-10

In this article, we derive low-complexity behavioral analytical models of the mutual inductance between coupling coils wireless power transfer systems (WPTSs), as functions their reciprocal position. These are extremely useful in characterization and design optimization WPTSs. Multiobjective genetic programming algorithm is adopted to generate ensuring an optimal tradeoff accuracy complexity. The training validation datasets needed for generation here obtained by performing numerical full...

10.1109/tie.2019.2962432 article EN cc-by IEEE Transactions on Industrial Electronics 2020-02-11

Abstract The paper presents an overview of the design status Radial Neutron Camera (RNC), that, together with Vertical Camera, will provide, through reconstruction techniques applied to measured line-integrated neutron fluxes, time resolved measurement ITER and α-source profile (i.e. emissivity, neutrons emitted per unit volume). RNC is composed two subsystems, In-Port Ex-Port located, respectively, inside outside Plug Equatorial Port #01. subsystem in a more advanced stage since it has...

10.1007/s10894-022-00333-9 article EN cc-by Journal of Fusion Energy 2022-09-18
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