A5082808700- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Particle accelerators and beam dynamics
- Ionosphere and magnetosphere dynamics
- Plasma Diagnostics and Applications
- Laser-Plasma Interactions and Diagnostics
- Nuclear reactor physics and engineering
- Atomic and Molecular Physics
- Laser-induced spectroscopy and plasma
- Solar and Space Plasma Dynamics
- Atomic and Subatomic Physics Research
- Particle Accelerators and Free-Electron Lasers
- Nuclear Physics and Applications
- Nuclear Materials and Properties
- Spectroscopy and Laser Applications
- High-Energy Particle Collisions Research
- Silicon and Solar Cell Technologies
- Electron and X-Ray Spectroscopy Techniques
- Semiconductor materials and devices
- Electrostatic Discharge in Electronics
- Target Tracking and Data Fusion in Sensor Networks
- Fault Detection and Control Systems
- Superconducting and THz Device Technology
- Gas Dynamics and Kinetic Theory
National Agency for New Technologies, Energy and Sustainable Economic Development
2015-2024
Institute of Ionized Gas
1990-2024
University of Padua
1995-2024
Culham Science Centre
2005-2024
University of Rome Tor Vergata
2024
Culham Centre for Fusion Energy
2005-2024
CEA Cadarache
1997-2023
Commissariat à l'Énergie Atomique et aux Énergies Alternatives
1997-2023
Institute for the Science and Technology of Plasmas
2023
National Centre for Nuclear Research
2021
The behaviour of tungsten in the core hybrid scenario plasmas JET with ITER-like wall is analysed and modelled a combination neoclassical gyrokinetic codes. In these discharges, good confinement conditions can be maintained only for first 2?3?s high power phase. Later W accumulation regularly observed, often accompanied by onset magneto-hydrodynamical activity, particular tearing modes (NTMs), both which have detrimental effects on global energy confinement. dynamics process examined, taking...
The dependence of plasma transport and confinement on the main hydrogenic ion isotope mass is fundamental importance for understanding turbulent and, therefore, accurate extrapolations from present tokamak experiments, which typically use a single hydrogen isotope, to burning plasmas such as ITER, will operate in deuterium–tritium mixtures. Knowledge properties edge barrier formation species critical view initial, low-activation phase ITER operations or helium its implications subsequent...
Recent developments in theory-based modelling of core heavy impurity transport are presented, and shown to be necessary for quantitative description present experiments JET ASDEX Upgrade. The treatment impurities is complicated by their large mass charge, which result a strong response plasma rotation or any small background electrostatic field the plasma, such as that generated anisotropic external heating. These forces lead poloidal asymmetries density, have recently been added numerical...
The scan of ion cyclotron resonant heating (ICRH) power has been used to systematically study the pump out effect central electron on impurities such as Ni and Mo in H-mode low collisionality discharges JET. transport parameters have measured by introducing a transient perturbation their densities via laser blow off technique. Without ICRH density profiles are typically peaked. application induces plasma centre (at normalized poloidal flux ρ = 0.2) an outward drift approximately proportional...
Abstract Ion cyclotron resonance frequency (ICRF) heating has been an essential component in the development of high power H-mode scenarios Jet European Torus ITER-like wall (JET-ILW). The ICRF performance was improved by enhancing antenna-plasma coupling with dedicated main chamber gas injection, including preliminary minimization RF-induced plasma-wall interactions, while RF where optimized for core impurity screening terms ion position and minority hydrogen concentration. impact on...
The evolution of the JET high performance hybrid scenario, including central accumulation tungsten (W) impurity, is reproduced with predictive multi-channel integrated modelling over multiple confinement times using first-principle based core transport models.8 channels ( , ) are modelled predictively, self-consistent sources, radiation and magnetic equilibrium, yielding a system non-linearities: This can reproduce observed radiative temperature collapse after several times.W transported...
Impurity injection in the JET ELMy H-mode regime has produced high-confinement, quasi-steady-state plasmas with densities close to Greenwald density. However, at large Ar densities, a sudden loss of confinement is observed. A possible correlation between and observed MHD phenomena, both core edge plasma, was considered. The degradation coincided impurity profile peaking following disappearance sawtooth activity. In addition, density analysis confirmed that central modes prevented peaking....
Stable operation with control on magnetohydrodynamic modes has been obtained in the modified reversed field experiment employing a set of 192 feedback controlled saddle coils. Improvements plasma temperature, confinement (twofold), and pulse length (threefold) and, as consequence magnetic fluctuation reduction, strong mitigation plasma-wall interaction mode locking are reported.Received 27 January 2006DOI:https://doi.org/10.1103/PhysRevLett.97.075001©2006 American Physical Society
The RFX-mod machine (Sonato et al 2003 Fusion Eng. Des. 66 161) recently achieved, for the first time in a reversed-field pinch, high plasma current up to 1.6 MA with good confinement. Magnetic feedback control of magnetohydrodynamic instabilities was essential reach goal. As is raised, spontaneously accesses new helical state, starting from turbulent multi-helical conditions. Together this raise, ratio between dominant and secondary mode amplitudes increases continuous way. This brings...
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...
Recent progress in the understanding and prediction of tungsten behaviour core JET H-mode plasmas with ITER-like wall is presented. Particular emphasis given to impact poloidal asymmetries impurity density. In particular, it shown that predicted reduction temperature screening induced by presence low field side localization density produced centrifugal force consistent observed a discharge baseline scenario. This provides first evidence role reducing strength screening. The main differences...
An intensive integrated modelling work of the main scenarios new Divertor Tokamak Test (DTT) facility with a single null divertor configuration has been performed using first principle quasi-linear transport models, in support design device and definition its scientific programme. First results this on DTT (R0 = 2.14 m, 0.65 m) are presented here along outcome gyrokinetic simulations used to validate reduced models range parameters. As result work, heating mix defined, size increased R0 2.19...
This paper describes the behavior of nickel in low confinement (L-mode) and high (H-mode) Joint European Torus (JET) discharges [P. J. Lomas, Plasma Phys. Control. Fusion 31, 1481 (1989)] characterized by application radio-frequency (rf) power heating featuring ITER (International Thermonuclear Experimental Reactor) relevant collisionality. The impurity transport is analyzed on basis perturbative experiments (laser blow off injection) compared with electron heat deuterium transport. In JET...
We present an overview of FTU experiments on runaway electron (RE) generation and control carried out through a comprehensive set real-time (RT) diagnostics/control systems newly installed RE diagnostics. An imaging spectrometer system detects visible infrared synchrotron radiation. A Cherenkov probe measures escaping the plasma. gamma camera provides hard x-ray radial profiles from bremsstrahlung interactions in Experiments onset suppression show that threshold electric field for is larger...
Disruption-generated runaway electron (RE) beams represent a severe threat for tokamak plasma-facing components in high current devices like ITER, thus motivating the search of mitigation techniques. The application 3D fields might aid this purpose and recently was investigated also ASDEX Upgrade experiment by using internal active saddle coils (termed B-coils). Resonant magnetic perturbations (RMPs) with dominant toroidal mode number n = 1 have been applied B-coils, RE specific scenario,...
RFX-mod is a reversed field pinch (RFP) experiment equipped with system that actively controls the magnetic boundary. In this paper we describe results of new control algorithm, clean mode (CMC), in which aliasing sideband harmonics generated by discrete saddle coils corrected real time. CMC operation leads to smoother (i.e. more axisymmetric) Tearing modes rotate (up 100 Hz) and partially unlock. Plasma–wall interaction diminishes due decrease non-axisymmetric shift plasma column. With...
Experimental observations on core particle and impurity transport from the Axial Symmetric Divertor Experiment Upgrade [O. Gruber, H.-S. Bosch, S. Günter et al., Nucl Fusion 39, 1321 (1999)] Joint European Torus [J. Pamela, E. R. Solano, JET EFDA Contributors, Nucl. 43, 1540 (2003)] tokamaks are reviewed compared. Robust general experimental behaviors observed in both devices related parametric dependences identified. The compared with most recent theoretical results field of transport.
Recent JET experiments have been devoted to the study of (3He)–D plasmas involving radio frequency (RF) heating. This paper starts by discussing RF heating efficiency theoretically expected in such plasmas, covering both relevant aspects wave and particle dynamics. Then it gives a concise summary main conclusions drawn from recent that were either focusing on studying physics or adopting as tool plasma behavior. Depending minority concentration chosen, different physical phenomena are...
With the exploration of MA plasma current regime in up to 0.5 s long discharges, RFX-mod has opened new and very promising perspectives for reversed field pinch (RFP) magnetic configuration, made significant progress understanding improving confinement controlling stability. A big leap with respect previous knowledge expectations on RFP physics performance been by since last 2006 IAEA Fusion Energy Conference. self-organized helical equilibrium experimentally achieved (the Single Helical...
Ion cyclotron resonance heating (ICRH) in the hydrogen minority scheme provides central ion and acts favorably on core tungsten transport. Full wave modeling shows that, at medium power level (4 MW), after collisional redistribution, ratio of transferred to ions electrons vary little with (hydrogen) concentration nH/ne but high-Z impurity screening provided by fast temperature increases concentration. The radiated JET discharges has been analyzed a large database covering 2013–2014 campaign....
Abstract In tokamaks, the role of turbulent transport heavy impurities, relative to that neoclassical transport, increases with increasing size plasma, as clarified by means general scalings, which use ITER standard scenario parameters reference, and actual results from a selection discharges ASDEX Upgrade JET. This motivates theoretical investigation properties convection impurities nonlinear gyrokinetic simulations in experimentally relevant conditions comparable ion electron heat fluxes....
During the 2015-2016 JET campaigns many efforts have been devoted to exploration of high-performance plasma scenarios envisaged for DT operation in JET.In this paper we review various key recent hybrid discharges and model combined ICRF+NBI heating.These deuterium with beams had ICRF antenna frequency tuned match cyclotron minority H at centre tokamak coinciding second harmonic resonance D. The modelling takes into account synergy between NBI heating through D beam ions which allows us...