F. Mirizzi

ORCID: 0000-0001-5374-7763
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About
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Research Areas
  • Magnetic confinement fusion research
  • Particle accelerators and beam dynamics
  • Superconducting Materials and Applications
  • Gyrotron and Vacuum Electronics Research
  • Ionosphere and magnetosphere dynamics
  • Fusion materials and technologies
  • Plasma Diagnostics and Applications
  • Microwave Engineering and Waveguides
  • Antenna Design and Analysis
  • Laser-Plasma Interactions and Diagnostics
  • Electromagnetic Launch and Propulsion Technology
  • Electromagnetic Simulation and Numerical Methods
  • Laser-induced spectroscopy and plasma
  • Electromagnetic Scattering and Analysis
  • Physics of Superconductivity and Magnetism
  • Space Satellite Systems and Control
  • Catalysis for Biomass Conversion
  • Dust and Plasma Wave Phenomena
  • Pulsed Power Technology Applications
  • Full-Duplex Wireless Communications
  • Plant Surface Properties and Treatments
  • Antenna Design and Optimization
  • Particle Detector Development and Performance
  • Magnetic Field Sensors Techniques
  • Advanced Antenna and Metasurface Technologies

University of Rome Tor Vergata
2018-2024

Consorzio CREO (Italy)
2014-2023

Istituto Nazionale di Fisica Nucleare, Laboratori Nazionali di Frascati
2023

University of Bari Aldo Moro
2018

National Agency for New Technologies, Energy and Sustainable Economic Development
2006-2016

ENEA Frascati Research Centre
1999-2016

Tecnic (Italy)
2014-2015

University of Naples Federico II
2013-2014

CEA Cadarache
2005-2012

Commissariat à l'Énergie Atomique et aux Énergies Alternatives
2005-2012

A 20 MW/5 GHz lower hybrid current drive (LHCD) system was initially due to be commissioned and used for the second mission of ITER, i.e. Q = 5 steady state target. Though not part currently planned procurement phase, it is now under consideration an earlier delivery. In this paper, both physics technology conceptual designs are reviewed. Furthermore, appropriate work plan also developed. This design, R&D, installation a MW LHCD on ITER follows Scientific Technical Advisory Committee...

10.1088/0029-5515/49/7/075001 article EN Nuclear Fusion 2009-05-27

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...

10.1088/0029-5515/50/9/095005 article EN Nuclear Fusion 2010-07-30

Biocatalytic processes are increasingly playing a key role in the development of sustainable asymmetric syntheses, which central to pharmaceutical companies for production chiral enantiopure drugs. This work describes simple and economically viable chemoenzymatic process (S)-rivastigmine, is an important drug treatment mild moderate dementia Alzheimer’s type. The described protocol involves R-regioselective bioreduction aromatic ketone by Lactobacillus reuteri DSM 20016 whole cells phosphate...

10.3390/catal8020055 article EN Catalysts 2018-01-31

A new ITER-relevant lower hybrid current drive (LHCD) launcher, based on the passive-active-multijunction (PAM) concept, was brought into operation Tore Supra tokamak in autumn 2009. The PAM launcher concept designed view of ITER to allow efficient cooling waveguides, as required for long pulse operation. In addition, it offers low power reflection close cut-off density, which is very attractive ITER, where large distance between plasma and wall may bring density front values. first...

10.1088/0029-5515/50/11/112002 article EN Nuclear Fusion 2010-09-30

Since the 2012 IAEA-FEC Conference, FTU operations have been largely devoted to runaway electrons generation and control, exploitation of 140 GHz electron cyclotron (EC) system liquid metal limiter elements. Experiments on shown that measured threshold electric field for their is larger than predicted by collisional theory can be justified considering synchrotron radiation losses. A new control algorithm was developed tested in presence a current plateau, allowing minimize interactions with...

10.1088/0029-5515/55/10/104005 article EN cc-by Nuclear Fusion 2015-03-27

Electron temperatures in excess of 8 keV have been obtained by electron-cyclotron-resonance heating on FTU plasmas at peak densities up to $8\ifmmode\times\else\texttimes\fi{}{10}^{19}\mathrm{m}{}^{\ensuremath{-}3}$. The magnetic shear the plasma core is low or negative, and electron heat diffusivity remains at, below, Ohmic level $(0.2\mathrm{m}{}^{2}/\mathrm{s})$, spite very large power density $(10--20\mathrm{MW}/\mathrm{m}{}^{3})$ which produces extremely high temperature gradients (up...

10.1103/physrevlett.82.560 article EN Physical Review Letters 1999-01-18

A prototype passive active multijunction (PAM) launcher for lower hybrid (LH) waves conceptually similar to that foreseen ITER has been successfully tested on FTU at frequency f = 8 GHz. The power routinely and safely managed the maximum time allowed by LH plant (0.9 s) without any fault in transmission lines is 250 kW, corresponding 75 MW m−2 across antenna area very close design value of 270 kW or 80 m−2. achieved least 1.4 times larger than request, which would be only 52 m−2, if 33...

10.1088/0029-5515/45/9/008 article EN Nuclear Fusion 2005-08-23

Studies on the current-drive (CD) efficiency have been carried out in FTU tokamak with 8 GHz lower-hybrid waves up to line-averaged plasma density ${\overline{n}}_{e}>1\ifmmode\times\else\texttimes\fi{}{10}^{20}{\mathrm{m}}^{\ensuremath{-}3}$. High efficiencies, larger than $0.2\ifmmode\times\else\texttimes\fi{}{10}^{20}{\mathrm{m}}^{\ensuremath{-}2}\mathrm{A}/\mathrm{W}$, are obtained for clean conditions, no significant degradation as is increased accessibility limit. The electron...

10.1103/physrevlett.82.93 article EN Physical Review Letters 1999-01-04

Strong electron internal transport barriers (ITBs) are obtained in FTU by the combined injection of lower hybrid (LH, up to 1.9 MW) and cyclotron (EC, 0.8 radio frequency waves. ITBs occur during either current plateau or ramp-up phase, both full partial drive (CD) regimes, peak densities ne0>1.2×1020 m−3, relevant ITER operation. Central temperatures Te0>11 keV, at ne0≈0.8×1020 m−3 sustained longer than 35 confinement times. The ITB extends over a region where slightly reversed magnetic...

10.1088/0029-5515/43/6/309 article EN Nuclear Fusion 2003-06-01

Steady internal transport barriers (ITBs) are obtained in FTU at ITER-relevant magnetic field and density (ne0 ≥ 1.3 × 1020 m−3) almost full non-inductive discharges, sustained by lower hybrid (LH) electron cyclotron (EC) RF waves sources. Similarly to ITER, only electrons directly heated which turn heat ions via collisions no momentum is injected. Collisions do not affect the mechanisms of turbulence suppression energy transport. At highest densities ion thermal conductivity remains ≤ ohmic...

10.1088/0029-5515/47/10/s10 article EN Nuclear Fusion 2007-09-18

Spontaneous increases in plasma density, up to ∼1.6 times the Greenwald value, are observed FTU with lithized walls. These plasmas characterized by profile peaking highest obtained densities. The transport analysis of these discharges shows a 20% enhancement energy confinement time, respect ITER97 L-mode scaling, correlated threshold factor. It has been found that 0.4 MW ECRH power, coupled at q = 2 surface, sufficient avoid disruptions 0.5 MA discharges. Direct heating magnetic islands...

10.1088/0029-5515/49/10/104013 article EN Nuclear Fusion 2009-09-09

The recent success in coupling lower hybrid (LH) waves high performance plasmas at JET together with the first demonstration on FTU of capability new passive active multijunction launcher removed major concerns possibility using LH ITER. exhibits highest experimental current drive (CD) efficiency low plasma temperature thus making it natural candidate for off-axis CD ITER where profile control will help maintaining burning a long-time scale. We review results: long internal transport barrier...

10.1088/0741-3335/47/12b/s26 article EN Plasma Physics and Controlled Fusion 2005-11-07

The MHD activity of plasma configurations with reversed magnetic shear has been investigated on the FTU tokamak. In presence pairs surfaces same rational value q = m/n safety factor, double-tearing modes are excited which give rise in most cases to bursts sawtooth-like profile rearrangements. More stable regimes have also found, is dominated by rotating saturated modes. a particular case and discharge without any detectable during current flat-top obtained. high-temperature ( at ), an...

10.1088/0741-3335/39/12b/029 article EN Plasma Physics and Controlled Fusion 1997-12-01
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