M. Recchia

ORCID: 0000-0002-2735-2466
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About
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Research Areas
  • Magnetic confinement fusion research
  • Particle accelerators and beam dynamics
  • Plasma Diagnostics and Applications
  • Superconducting Materials and Applications
  • Particle Accelerators and Free-Electron Lasers
  • Fusion materials and technologies
  • Ionosphere and magnetosphere dynamics
  • Gyrotron and Vacuum Electronics Research
  • Electromagnetic Launch and Propulsion Technology
  • Reliability and Maintenance Optimization
  • Software Reliability and Analysis Research
  • Advanced Data Storage Technologies
  • Laser-Plasma Interactions and Diagnostics
  • Software System Performance and Reliability
  • Muon and positron interactions and applications
  • Electromagnetic Compatibility and Measurements
  • Software Testing and Debugging Techniques
  • Magnetic Properties and Applications
  • Parallel Computing and Optimization Techniques
  • Electric Motor Design and Analysis
  • Induction Heating and Inverter Technology
  • High voltage insulation and dielectric phenomena
  • Atomic and Molecular Physics

National Agency for New Technologies, Energy and Sustainable Economic Development
2013-2024

University of Rome Tor Vergata
2024

University of Padua
2009-2023

Institute for the Science and Technology of Plasmas
2022-2023

Ghent University
2022

Istituto Nazionale di Fisica Nucleare, Laboratori Nazionali di Legnaro
2013-2019

Institute of Market Economy, Social Policy and Law
2013-2015

Istituto Nazionale di Fisica Nucleare
2015

University of Milan
2013

AT&T (United States)
2003-2004

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...

10.1088/1367-2630/aa78e8 article EN cc-by New Journal of Physics 2017-08-25

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...

10.1088/0029-5515/55/8/083025 article EN Nuclear Fusion 2015-07-21

Abstract The negative-ion based neutral beam injector for heating and current drive of the ITER plasma (ITER HNB) is under development, at present focusing on optimization full-scale source in SPIDER test stand. production H − or D ions ion low work function surfaces obtained by caesium evaporation. This paper describes conditioning procedure corresponding performances during first operation with caesium. Technical solutions to overcome limitations stand are described. influence parameters...

10.1088/1741-4326/ac715e article EN Nuclear Fusion 2022-05-23

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...

10.1088/1741-4326/ab2271 article EN Nuclear Fusion 2019-05-17

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...

10.1063/1.5133076 article EN Review of Scientific Instruments 2020-02-01

SPIDER is one of the two projects ITER Neutral Beam Test Facility (NBTF) under construction in Padova, Italy, at Consorzio RFX premises; it will have a 100 keV beam source with full-size prototype radiofrequency (RF) ion for Injector (NBI), designed to operate pulse length up 3600 s, featuring ITER-like filter field configuration, caesium oven layout and wide set diagnostics.These features allow reproducing operation like as cannot be done any other existing test facility.SPIDER realization...

10.1088/1741-4326/aa7490 article EN Nuclear Fusion 2017-05-22

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 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

Neutral Beam Injectors (NBIs), which need to be strongly optimized in the perspective of DEMO reactor, request a thorough understanding negative ion source used and multi-beamlet optics. A relatively compact radio frequency (rf) source, named NIO1 (Negative Ion Optimization 1), with 9 beam apertures for total H− current 130 mA, 60 kV acceleration voltage, was installed at Consorzio RFX, including high voltage deck an X-ray shield, provide test bench optimizations activities support ITER NBI...

10.1063/1.4932616 article EN Review of Scientific Instruments 2015-11-25

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,...

10.1088/1741-4326/aa61cc article EN Nuclear Fusion 2017-06-28

The Divertor Tokamak Test facility (DTT) will be a new experimental located at Frascati, Rome, Italy, whose main goal to have better understanding on hot plasma interactions with plasma-facing components (PFCs) and aid in the development of ITER successively DEMO. improved conceptual design beamline for DTT neutral beam heating (NBH) system is here overviewed, particular focus technical solutions adopted fulfill requirements maximize performances. proposed features providing deuterium...

10.1109/tps.2022.3162902 article EN IEEE Transactions on Plasma Science 2022-04-14

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...

10.1088/0741-3335/52/12/124023 article EN Plasma Physics and Controlled Fusion 2010-11-15

A 60 kV ion source (9 beamlets of 15 mA each H−) and plasma generators are being developed at Consorzio RFX INFN-LNL, for their versatility in experimental campaigns training. Unlike most sources, the design aimed continuous operation. Magnetic configuration can achieve a minimum |B| trap, smoothly merged with extraction filter. Modular allows quick substitution upgrading parts such as postacceleration grids or electrodes contact plasma. Experiments radio frequency generator Faraday cage...

10.1063/1.3670350 article EN Review of Scientific Instruments 2012-02-01

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...

10.1088/0029-5515/55/10/104012 article EN Nuclear Fusion 2015-07-29
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