A5074911979- Magnetic confinement fusion research
- Particle accelerators and beam dynamics
- Gyrotron and Vacuum Electronics Research
- Superconducting Materials and Applications
- Fusion materials and technologies
- Ionosphere and magnetosphere dynamics
- Plasma Diagnostics and Applications
- Advanced Radiotherapy Techniques
- Microwave Engineering and Waveguides
- Nuclear reactor physics and engineering
- Laser-Plasma Interactions and Diagnostics
- Medical Imaging Techniques and Applications
- Physics of Superconductivity and Magnetism
- Radiation Dose and Imaging
- Laser-induced spectroscopy and plasma
- Nuclear Physics and Applications
- Power Line Communications and Noise
- Atomic and Subatomic Physics Research
- Anomaly Detection Techniques and Applications
- Network Security and Intrusion Detection
- Radiation Detection and Scintillator Technologies
- Acoustic Wave Resonator Technologies
- Air Quality Monitoring and Forecasting
- Particle Accelerators and Free-Electron Lasers
- Glass properties and applications
National Agency for New Technologies, Energy and Sustainable Economic Development
2005-2025
National Research Council
2015-2024
Institute for the Science and Technology of Plasmas
2020-2024
Institute of Plasma Physics
2008-2019
Max Planck Society
2016
Max Planck Institute for Plasma Physics
2016
Institute of Applied Physics
2016
Karlsruhe Institute of Technology
2011-2013
Fusion for Energy
2008-2011
École Polytechnique Fédérale de Lausanne
2008-2009
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...
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...
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...
ABSTRACT OBJECTIVE/SCOPE Methane emissions in Oil & Gas facilities are a significant concern due to methane's high global warming potential (GWP-100 of 28). Precise detection and quantification methane essential for effective mitigation. Traditionally, monitoring is performed by operators using hand-held Optical Imaging (OGI) cameras, which used hydrocarbon leak detection. However, this method exposes personnel harsh environments, congested spaces, potentially explosive atmospheres,...
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...
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...
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.
The intrinsic limited toroidal electric field (0.3 V m−1) in devices with superconducting poloidal coils (ITER, JT-60SA) requires additional heating, like electron cyclotron (EC) waves, to initiate plasma and sustain it during the burn-through phase. FTU tokamak has contributed studying perspective of EC assisted breakdown. Afterward, a new experimental modeling activity addressing study start-up configuration close ITER one (magnetic field, oblique injection, polarization) been performed is...
The Italian tokamak DTT (Divertor Tokamak Test) is a facility for research on nuclear fusion with the aim of investigating alternative power exhaust solutions to be exploited in future DEMO plant. foresees three additional heating systems provide plasma sufficient power: Electron Cyclotron Heating (ECH) main one, up 32 MW installed. It consists 4 clusters, each one composed eight radio-frequency sources (gyrotrons) their single-beam transmission lines, quasi-optical Multi-Beam Transmission...
To achieve efficient power transfer, the Divertor Tokamak Test (DTT) facility relies on supplementary heating systems. One of them is Electron Cyclotron Heating (ECH). ECH employs 4 clusters, each comprising 8 gyrotrons as Radio Frequency (RF) sources, 1 quasi-optical Multi-Beam Transmission Line (MBTL), and independent launchers. The generated RF (170 GHz, MW, 100 s) delivered to plasma through oversized flat focusing mirrors. However, MBTL faces challenges during operation microwave beams...
The JT-60SA tokamak, being built under the Broader Approach agreement jointly by Europe and Japan, is due to start operation in 2020 expected give substantial contributions both ITER DEMO scenario optimisation. A broad set of preparation activities for an efficient experiments on carried out, involving elaboration Research Plan, advanced modelling various domains, feasibility conception studies diagnostics other sub-systems connection with priorities scientific programme, development...
For the development of a DEMOnstration Fusion Power Plant design auxiliary heating systems is key activity in order to achieve controlled burning plasma. The present mix considers electron cyclotron resonance (ECRH), neutral beam injection (NBI) and ion (ICRH) with target power plasma about 50 MW for each system. main tasks assigned EC system are breakdown assisted start-up, L-H transition current ramp up burn, MHD stability control assistance down. consequent requirements used conceptual...
JT-60SA, the largest tokamak that will operate before ITER, has been designed and built jointly by Japan Europe, is due to start operation in 2020.Its main missions are support ITER exploitation contribute demonstration fusion reactor machine scenario design.Peculiar properties of JT-60SA its capability produce long-pulse, high-β, highly shaped plasmas.The preparation Research Plan, plasma scenarios, producing physics results not only relevant future experiments, but often constitute...
JT-60SA envisions electron cyclotron wall conditioning (ECWC), as method in the presence of toroidal field to control fuel and impurity recycling improve plasma performance reproducibility. This paper reports on Helium ECWC experiments TCV support operation. Nearly sixty discharges have been successfully produced TCV, at a B T = 1.3 or 1.54 T, with gyrotrons 82.7 GHz X2 mode, mimicking operation second harmonic EC wave. Discharge parameters were tuned order (i) minimize time for onset...
The Divertor Tokamak Test (DTT) facility, whose construction has started in Frascati (Italy), will be equipped with an ECRH (electron cyclotron resonance heating) system including 32 gyrotrons as microwave power sources. procurement of the first batch sources 16 MW total power, based on 170 GHz/≥ 1 MW/100 s vacuum tubes, is progress and available for DTT plasma. organized into four clusters 8 each. transmitted from Gyrotron Hall to Torus Building (THB) by a quasioptical transmission line...