Francesco Lunardon

ORCID: 0000-0002-9339-2482
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About
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Research Areas
  • Magnetic confinement fusion research
  • Superconducting Materials and Applications
  • Particle accelerators and beam dynamics
  • Plasma Diagnostics and Applications
  • Physics of Superconductivity and Magnetism
  • Frequency Control in Power Systems
  • Fusion materials and technologies
  • Nuclear Physics and Applications
  • Control Systems and Identification
  • Target Tracking and Data Fusion in Sensor Networks
  • HVDC Systems and Fault Protection
  • Advanced DC-DC Converters
  • Fault Detection and Control Systems
  • Superconductivity in MgB2 and Alloys

National Agency for New Technologies, Energy and Sustainable Economic Development
2019-2024

University of Padua
2019-2023

Ghent University
2023

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...

10.1088/1741-4326/ab1c6a article EN Nuclear Fusion 2019-04-25

An overview of the recent operations and main results cesium injection in Source for Production Ions Deuterium Extracted from Rf plasma (SPIDER) negative ion source are described this contribution. In experiments without injection, all SPIDER plants were tested to verify basic expectations on operational parameters (e.g., electron cooling effectiveness magnetic filter field) determine its region. For beam properties, it was shown that current density varies across vertical direction....

10.1109/tps.2022.3226239 article EN IEEE Transactions on Plasma Science 2023-01-20

The EU DEMO Plant Electrical System (PES) main scopes are to supply all the plant electrical loads and deliver Power Transmission Grid (PTG) net power generated. studies on PES during Pre-Concept Design (PCD) Phase were mainly addressed understand possible issues, related special features both of generated, with respect a same size, be supplied loads. For this purpose, approach was start design different components adopting technologies already utilized in fusion experiments Nuclear Plants...

10.1016/j.fusengdes.2022.113052 article EN cc-by Fusion Engineering and Design 2022-02-12

The Plant Electrical System (PES) of the European DEMOnstration fusion power plant (DEMO), presently under conceptual design, shall supply to loads and deliver net Power Transmission Grid (PTG). Starting from available requirements, applicability DEMO PES technologies design approaches adopted in ITER nuclear plants (NPP) has been evaluated. This article presents results survey proposes alternative solutions deal with identified criticalities.

10.1109/tps.2024.3362198 article EN IEEE Transactions on Plasma Science 2024-02-21

Fusion-fission hybrid reactors are seen as a possible, mid-term, CO <sub xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">2</sub> -free energy source. Starting from the progress in understanding reversed field pinch plasma confinement, pilot neutron source with configuration of R = 4 m and 0.8 current up to 14 mega-ampére (MA) is proposed. A staged experimental approach, increased complexity investment, was identified tackle existing issues related...

10.1109/tps.2019.2957888 article EN IEEE Transactions on Plasma Science 2020-01-01

Abstract Three years of experiments on SPIDER allowed characterization the main features source plasma and negative ion beam, in original design configuration. For large dimensions chamber, extraction area, investigation single-beamlet currents uniformity had to be carried out extend knowledge gained smaller prototype sources. The configuration multiple RF drivers filter field topologies were found cause a peculiar behavior confinement drivers, creating left-right asymmetries which also...

10.1088/1748-0221/18/09/c09001 article EN cc-by Journal of Instrumentation 2023-09-01

At the International Thermonuclear Experimental Reactor (ITER) Neutral Beam Test Facility in Padua (Italy), ion source full-scale prototype—SPIDER—has been operation since June 2018 and, as of March 2021, has begun to explore range beam energies exceeding 30 keV. This revealed a number novel issues with power supplies and extractor, mainly associated grid breakdowns. Those include set high current single quadrant resonant converters, known support (ISSSs) voltage pulse step modulator feeding...

10.1109/tps.2022.3173820 article EN IEEE Transactions on Plasma Science 2022-05-19

The Magnetic Energy Storage and Transfer system (MEST) aims at improving the power handling in supplying SuperConducting (SC) coils of fusion experiments. It is based on smart use Superconducting technology allows introduction a certain degree decoupling between grid load. MEST operation storage transfer needed energy Load Coil (LC) an additional inductor named Sink (KC); realized via capacitors switched by fully controllable semiconductors. This paper focuses control proposes strategy, two...

10.1016/j.fusengdes.2023.113616 article EN cc-by Fusion Engineering and Design 2023-03-16

The magnetic energy storage and transfer (MEST) system is a newly developed scheme to supply the superconducting (SC) coils in large-size tokamak reversed field pinch (RFP) reactors cope with issues related electrical power handling these applications. It very promising alternative face both high active peaks, required during plasma formation control, huge reactive demand, linked use of thyristor converters. MEST operating principle control strategy supplying single SC coil have already been...

10.1109/tps.2024.3387356 article EN IEEE Transactions on Plasma Science 2024-04-26

The reversed field pinch (RFP) could be a valid basis for the 14.1-MeV neutron source as required in fusion–fission hybrid reactors (FFHRs). use of superconductors an RFP reactor, although mandatory magnetizing/equilibrium coils, represent issue due to their limitations allowed magnetic derivative, which is quite high during initial plasma current phase operation. A new concept proposed based on double-coil system: first made with and other conventional copper coils. basic principle...

10.1109/tps.2022.3179291 article EN IEEE Transactions on Plasma Science 2022-06-14

RFX-mod is an experimental fusion device, which contributes to plasma physics studies both in reversed field pinch (RFP) and tokamak configurations. Its high flexibility, due active magnetohydrodynamic (MHD) control system the modular coils power supply (CPS) system, allowed operating a wide range of conditions with current up 2 MA. Experiments such study on new promising confinement regimes, dominated by self-organization process generation helical structure core. Presently, under...

10.1109/tps.2022.3195538 article EN IEEE Transactions on Plasma Science 2022-08-26
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