A. Bruschi
A5063999769- Particle accelerators and beam dynamics
- Magnetic confinement fusion research
- Gyrotron and Vacuum Electronics Research
- Superconducting Materials and Applications
- Microwave Engineering and Waveguides
- Plasma Diagnostics and Applications
- Ionosphere and magnetosphere dynamics
- Fusion materials and technologies
- Nuclear reactor physics and engineering
- Laser-Plasma Interactions and Diagnostics
- Physics of Superconductivity and Magnetism
- Particle Accelerators and Free-Electron Lasers
- Radio Frequency Integrated Circuit Design
- Atomic and Subatomic Physics Research
- Advanced DC-DC Converters
- Laser-induced spectroscopy and plasma
- Solar and Space Plasma Dynamics
- Pulsed Power Technology Applications
- Acoustic Wave Resonator Technologies
- Advanced Power Amplifier Design
- Electrostatic Discharge in Electronics
- Electromagnetic Scattering and Analysis
- Semiconductor materials and devices
- Radio Astronomy Observations and Technology
- Metal and Thin Film Mechanics
Institute for the Science and Technology of Plasmas
2020-2024
National Research Council
2009-2024
Italian Institute of Technology
2024
National Academies of Sciences, Engineering, and Medicine
2015-2023
Institute of Plasma Physics
2009-2019
National Agency for New Technologies, Energy and Sustainable Economic Development
1999-2016
Institute of Applied Physics
2009-2016
Russian Academy of Sciences
2007-2011
Karlsruhe Institute of Technology
2011
Fusion for Energy
2008-2011
The European DEMO is a pulsed device with pulse length of 2 hours. functions devoted to the heating and current drive system are: plasma breakdown, ramp-up flat-top where fusion reactions occur, control during phase, finally ramp-down. EU-DEMO project was in Pre-Concept Design Phase 2014-2020, meaning that some cases, design values precise requirements from physics point view were not yet frozen. A total 130 MW considered for all phases plasma: flat top, 30 required neoclassical tearing...
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...
The ITER electron cyclotron (EC) upper port antenna (or launcher) is nearing completion of the detailed design stage and final build-to-print will soon start. main objective this launcher to drive current locally stabilize neoclassical tearing modes (NTMs) (depositing ECCD inside island that forms on either q = 3/2 or 2 rational magnetic flux surfaces) control sawtooth instability (deposit near 1 surface). should be capable steering focused beam deposition location resonant surface over...
The European Union is working toward providing 2-MW, coaxial-cavity, continuous-wave (cw) 170-GHz gyrotrons for ITER. Their design based on results from an experimental preprototype tube having a pulse length of several milliseconds, in operation at Forschungszentrum Karlsruhe (FZK) years now. first industrial prototype was designed cw but, phase, aimed 1 s the Gyrotron Test Facility Lausanne, Switzerland, as part phased testing/development program (1 s, 60 cw). this gyrotron are reported...
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...
An innovative cooling strategy for the mirrors of transmission line electron cyclotron heating (ECH) a fusion research reactor, divertor tokamak test (DTT) facility, is presented and investigated here based on triply periodic minimal surfaces (TPMSs). After check manufacturability gyroid Split-P lattices unit cell size ranging from 3 to 8 mm, extensive numerical investigations by conjugate heat transfer analyses have been performed. The removal capability has assessed together with pressure...
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...
The Divertor Tokamak Test (DTT) facility is being realised in Frascati, Italy for the study of power exhaust issues view DEMO tokamak. A multi-MW Electron Cyclotron Resonance Heating (ECRH) system foreseen with a first set 16 gyrotrons at 1 MW and 170 GHz available stage operation; additional from to 1.2 are later total up 33.6 ECRH plasma. itself part 45 external heating coupled plasma, provided also by Ion Neutral Beam Injection. Transmission Line (TL) fully quasi-optical, between 84 m 138...
The EU DEMO Tokamak is foreseen to be equipped with an electron cyclotron (EC) system for plasma heating, magnetohydrodynamic (MHD) control, and thermal instability suppression. Up six launchers will installed into equatorial ports the aim inject a maximum of 130 MW millimeter wave power at frequencies 136/170/204 GHz toward dedicated positions plasma. This article presents current layout typical EC launcher components within available space reservation areas in level baseline model. Beside...
Abstract The European DEMO (EU-DEMO) reactor studies within EUROfusion aim to develop a fusion power plant concept. large tokamak device needs an auxiliary heating which, at the present stage, is provided by Electron Cyclotron (EC) system with up 130 MW foreseen reach different regions of plasma for heating, suppression instabilities and possibility support ramp-up ramp-down phases. conceptual design based on 2 coaxial-cavity gyrotron sources, transmission line (TL) using both circular...
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...
A fast directional switch (FADIS) is described, which allows controlled switching of high-power microwaves between two outputs. possible application could be synchronous stabilization neoclassical tearing modes (NTMs). Generally, the device can used to share installed EC power different types launchers or applications (e.g. in ITER, midplane/upper launcher). The performed electronically without moving parts by a small frequency-shift keying gyrotron (some tens megahertz), and narrow-band...
AbstractThe development of electron cyclotron resonance heating (ECRH)-electron current drive (ECCD) as a tool for suppression plasma instabilities requires that the millimeter-wave beams used testing magnetohydrodynamic (MHD) stabilization schemes ITER be able to follow magnetic island position in real time. In FTU tokamak, design new ECRH fast-steerable launcher will enable fast-controlled deposition at precise poloidal location and inclusion mirror motion feedback loop aimed MHD...
On the FTU tokamak, collective Thomson scattering (CTS) diagnostic was renewed for investigating possible excitation of parametric decay instabilities (PDI) by electron cyclotron (EC) or CTS probe beams in presence magnetic islands and measure their effects on EC power absorption.
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...
Improvement (up to a factor of approximately 4) the electron-cyclotron (EC) current drive efficiency in plasmas sustained by lower-hybrid (LH) has been demonstrated stationary conditions on Tore Supra tokamak. This was made possible feedback controlled discharges at zero loop voltage, constant plasma current, and density. effect, predicted kinetic theory, results from favorable interplay velocity space diffusions induced two waves: EC wave pulling low-energy electrons out Maxwellian bulk, LH...