A5067944023- Magnetic confinement fusion research
- Ionosphere and magnetosphere dynamics
- Particle accelerators and beam dynamics
- Superconducting Materials and Applications
- Fusion materials and technologies
- Laser-Plasma Interactions and Diagnostics
- Plasma Diagnostics and Applications
- Gyrotron and Vacuum Electronics Research
- Optimal Power Flow Distribution
- Nuclear reactor physics and engineering
- Dust and Plasma Wave Phenomena
- Microgrid Control and Optimization
- Smart Grid Energy Management
- Solar and Space Plasma Dynamics
- Physics of Superconductivity and Magnetism
- Power System Optimization and Stability
- Laser-induced spectroscopy and plasma
- Smart Grid Security and Resilience
- Power Line Communications and Noise
- Metal and Thin Film Mechanics
- Electric Power System Optimization
- High-pressure geophysics and materials
- Geomagnetism and Paleomagnetism Studies
- Transportation Systems and Safety
- Magneto-Optical Properties and Applications
National Agency for New Technologies, Energy and Sustainable Economic Development
2003-2025
Institute of Plasma Physics
2009-2024
Institute for the Science and Technology of Plasmas
2019-2024
Lucerne University of Applied Sciences and Arts
2021-2024
University of Rome Tor Vergata
2024
Culham Science Centre
2024
Culham Centre for Fusion Energy
2024
National Research Council
2018-2021
University of British Columbia
2017-2020
Okanagan University College
2017-2020
Abstract The JET hybrid scenario has been developed from low plasma current carbon wall discharges to the record-breaking Deuterium-Tritium plasmas obtained in 2021 with ITER-like Be/W wall. development started pure Deuterium refinement of current, and toroidal magnetic field choices succeeded solving heat load challenges arising 37 MW injected power ITER like environment, keeping radiation edge core controlled, avoiding MHD instabilities reaching high neutron rates. have re-run Tritium...
A selection of achievements and first physics results are presented the European Integrated Tokamak Modelling Task Force (EFDA ITM-TF) simulation framework, which aims to provide a standardized platform an integrated modelling suite validated numerical codes for prediction complete plasma discharge arbitrary tokamak.The framework developed by ITM-TF, based on generic data structure including both simulated experimental data, allows development sophisticated simulations (workflows)...
Abstract In this work the onset of tearing modes in termination phase plasma pulses on JET is investigated. It shown that broadening or shrinking current density profile, as a consequence core hollowing an edge cooling electron temperature strongly increases probability destabilizing 2/1 mode also absence external trigger (e.g. sawtooth crash). Two parameters are defined to highlight changes shape profile can lead MHD instabilities and empirical stability diagram introduced into space two...
The mechanisms of nonlinear interaction external helical fields with a rotating plasma are investigated analyzing the results recent systematic experiments on Joint European Torus (JET) [A. Gibson et al., Phys. Plasmas 5, 1839 (1998)] that widen previous data base collected Compass-D [T. C. Hender Nucl. Fusion 32, 2091 (1992)], Doublet III-D [R. J. La Haye 2119 (1992)] and JET. empirical scaling laws governing onset “error field” locked modes re-assessed interpreted in terms existing driven...
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...
This paper presents a measurement-based method to determine distributed energy resource (DER) active- and reactive-power setpoints that minimize bus voltage deviations from prescribed reference values, desired setpoints, as well cost of DER outputs. Central the proposed is estimation linear sensitivity model synchronized power-injection data collected distribution-level phasor measurement units installed at only subset buses in distribution system. As new measurements become available,...
Abstract Deuterium plasma discharges of the Divertor Tokamak Test facility (DTT) in different operational scenarios have been predicted by a comprehensive first-principle based integrated modelling activity using state-of-art quasi-linear transport models. The results this work refer to updated DTT configuration, which includes device size optimisation (enlargement <?CDATA $R_0 = {2.19}$?> <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:msub>...
Abstract This paper reports the first experiment carried out in deuterium–tritium addressing integration of a radiative divertor for heat-load control with good confinement. Neon seeding was time D–T plasma as part second campaign JET its Be/W wall environment. The technical difficulties linked to re-ionisation heat load are reported T and D–T. compares impact neon on plasmas their D counterpart detachment, localisation radiation, scrape-off profiles, pedestal structure, edge localised modes global
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...
Tearing modes are MagnetoHydroDynamics (MHD) instabilities that reduce the performance of fusion devices. They can however be controlled and suppressed using electron cyclotron current drive (ECCD) as demonstrated in various tokamaks. In this work, simulations island stabilization by ECCD-driven have been carried out toroidal nonlinear 3D full MHD code xtor-2f, which a source term modeling ECCD has implemented. The efficiency parameter, , computed its variations with respect to width...
Abstract This paper is dealing with the physics basis used for design of Divertor Tokamak Test facility (DTT), under construction in Frascati (DTT 2019 DTT interim report (2019)) Italy, and description main target plasma scenarios device. The goal will be study power exhaust, intended as a fully integrated core-edge problem, eventually to propose an optimized divertor European DEMO plant. approach described their features are reported, by using simulations performed state-of-the-art codes...
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...
In today’s high frequency systems employed for plasma diagnostics, power heating, and current drive the behavior of wave beams is appreciably affected by self-diffraction phenomena due to their narrow collimation. present article three-dimensional propagation Gaussian in inhomogeneous anisotropic media analyzed, starting from a properly formulated dispersion relation. Particular attention paid, case electromagnetic electron cyclotron (EC) waves, toroidal geometry characterizing tokamak...
Disruption avoidance by stabilization of MHD modes through injection ECRH at different radial locations is reported. Disruptions have been induced in the FTU (Frascati Tokamak Upgrade) deuterium plasmas Mo or exceeding density limit (D gas puffing). triggered when ${V}_{\mathrm{loop}}$ exceeds a preset threshold value. Coupling between ($m/n=3/2$, $2/1$, $3/1$) occurs before disruption. Direct heating one coupled mode sufficient to avoid disruptions, while close leads disruption delay. These...
The use of ECRH has been investigated as a promising technique to avoid or postpone disruptions in dedicated experiments FTU and ASDEX Upgrade. Disruptions have produced by injecting Mo through laser blow-off (FTU) puffing deuterium gas above the Greenwald limit (FTU Upgrade). toroidal magnetic field is kept fixed launching mirrors steered before every discharge order change deposition radius. loop voltage signal used disruption precursor trigger power plasma current quench. In (Ip =...
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...
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...
The main effect of the Gaussian behavior an electromagnetic beam consists in a waist formation focal regions, where ordinary geometric optics would collapse. characteristic features beams, both when they interact with components transmission lines and propagate through inhomogeneous anisotropic media (as happens, for instance, case diagnostic or heating experiments magnetoactive plasmas fusion interest), are crucial relevance many technical scientific purposes. present paper is devoted to...
The problem of the trigger neoclassical tearing mode is addressed in this work by evaluating non-linear terms generalized Rutherford equation (GRE) for a set JET disruptions. linear stability index Δ′0, even positive values, not enough to describe as stabilizing effects tend prevent growth below certain width. First, an analysis on contribution effect curvature and destabilizing bootstrap done. Second, focuses role ion polarization current, return current that flows parallel magnetic field...
The formation of magnetic islands with mode numbers (m>1,n⩾1) apparently triggered by sawtooth crashes has for a long time been concern in JET discharges auxiliary heating as it affects the peak performance, terms stored energy or neutron yield (in DT experiments). phenomenological association crash onset resistive modes is particularly relevant context neo-classical tearing (NTM) theory that requires `seed' island above critical value. Relying on observations and an understanding role...
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...
Experiments on disruption avoidance have been carried out in H-mode ASDEX Upgrade plasmas: the localized perpendicular injection of ECRH (1.5 MW ∼ 0.2 P tot ) onto q = 2 resonant surface has led to delay and/or complete disruptions a high β N scenario ( I p 1 MA, B t 2.1 T, 95 3.6, with NBI ∼7.5 MW). In these discharges (at low and density) neoclassical tearing modes (NTMs) are excited: growth locking m / n 2/1 mode leads disruption. The scheme experiment is successfully applied same way as...