T. Bolzonella
A5062856948- Magnetic confinement fusion research
- Superconducting Materials and Applications
- Fusion materials and technologies
- Ionosphere and magnetosphere dynamics
- Particle accelerators and beam dynamics
- Plasma Diagnostics and Applications
- Laser-Plasma Interactions and Diagnostics
- Nuclear reactor physics and engineering
- Solar and Space Plasma Dynamics
- Physics of Superconductivity and Magnetism
- Plasma and Flow Control in Aerodynamics
- Particle Accelerators and Free-Electron Lasers
- Radiation Effects in Electronics
- Metal and Thin Film Mechanics
- Fault Detection and Control Systems
- Atomic and Subatomic Physics Research
- Silicon and Solar Cell Technologies
- Neural Networks and Applications
- Quantum chaos and dynamical systems
- Astronomical Observations and Instrumentation
- Anomaly Detection Techniques and Applications
- Control Systems and Identification
- Laser-induced spectroscopy and plasma
- Quantum, superfluid, helium dynamics
- Electron and X-Ray Spectroscopy Techniques
National Agency for New Technologies, Energy and Sustainable Economic Development
2012-2024
Institut de Recherche sur la Fusion par Confinement Magnétique
2024
CEA Cadarache
2024
University of Padua
2014-2024
National Centre for Nuclear Research
2021
Royal Military Academy
2020
Innova (Italy)
2019
Max Planck Institute for Plasma Physics
2015
Max Planck Society
2015
Institute of Ionized Gas
1998-2013
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...
Abstract A large scale program to develop a conceptual design for demonstration fusion power plant (DEMO) has been initiated in Europe. Central elements are the baseline points, which developed by system codes. The assessment of credibility these points is often hampered missing information. main physics and technology content central European codes have published (Kovari et al 2014 Fusion Eng. Des . 89 3054–69, 2016 104 9–20, Reux 2015 Nucl. 55 073011). In addition, this publication...
Abstract The tokamak à configuration variable (TCV) continues to leverage its unique shaping capabilities, flexible heating systems and modern control system address critical issues in preparation for ITER a fusion power plant. For the 2019–20 campaign configurational flexibility has been enhanced with installation of removable divertor gas baffles, diagnostic capabilities an extensive set upgrades new dual frequency gyrotrons. baffles reduce coupling between main chamber allow detailed...
The JT-60SA device has been designed as a highly shaped large superconducting tokamak with variety of plasma actuators (heating, current drive, momentum input, stability control coils, resonant magnetic perturbation W-shaped divertor, fuelling, pumping, etc) in order to satisfy the central research needs for ITER and DEMO. In ITER- DEMO-relevant parameter regimes DEMO-equivalent shapes, quantifies operation limits, responses operational margins terms MHD stability, transport confinement,...
Abstract The favorable confinement properties of negative-triangularity (NT) tokamak configurations were discovered in the TCV late 1990s and documented over two following decades, through investigations predominantly electron-heated plasmas limited topologies. most recent experimental campaign has marked a leap forward, characterized by development variety diverted NT shapes that are robustly stable with basic Ohmic heating. application auxiliary heating, directed now at both electrons ions...
We report the results of an experimental and theoretical international project dedicated to study quasi-single helicity (QSH) reversed field pinch (RFP) plasmas. The has involved several RFP devices numerical codes. It appears that QSH spectra are a robust feature common all experiments. Our expand reinforce evidence formation self-organized states with one dominant helical mode (Ohmic SH state) is approach complementary active control magnetic turbulence improve confinement in steady state RFP.
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...
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 TCV tokamak is augmenting its unique historical capabilities (strong shaping, strong electron heating) with ion heating, additional heating compatible high densities, and variable divertor geometry, in a multifaceted upgrade program designed to broaden operational range without sacrificing fundamental flexibility. rooted three-pronged approach aimed at ITER support, explorations towards DEMO, research. A 1 MW, tangential neutral beam injector (NBI) was recently installed promptly...
The objectives of the nuclear fusion power plant DEMO, to be built after ITER experimental reactor, are usually understood lie somewhere between those and a 'first kind' commercial plant. Hence, in DEMO issues related efficiency RAMI (reliability, availability, maintainability inspectability) among most important drivers for design, as cost electricity produced by this will strongly depend on these aspects. In framework EUROfusion Work Package Heating Current Drive within Power Plant Physics...
Scenario modelling for the demonstration fusion reactor (DEMO) has been carried out using a variety of simulation codes.Two DEMO concepts have analysed: pulsed tokamak, characterised by rather conventional physics and technology assumptions (DEMO1) steady-state with moderately advanced (DEMO2).Sensitivity to impurity concentrations, radiation, heat transport models investigated.For DEMO2, impact current driven non-inductively Neutral Beams studied full MonteCarlo simulations fast ion...
Abstract The research program of the TCV tokamak ranges from conventional to advanced-tokamak scenarios and alternative divertor configurations, exploratory plasmas driven by theoretical insight, exploiting device’s unique shaping capabilities. Disruption avoidance real-time locked mode prevention or unlocking with electron-cyclotron resonance heating (ECRH) was thoroughly documented, using magnetic radiation triggers. Runaway generation high- Z noble-gas injection runaway dissipation...
RFX-mod is a Reversed Field Pinch device that allowed performing experiments in regimes with plasma current up to 2 MA, thanks its MHD active control system. Experiments have shown improved performances are obtained when the resonant part of m = 1 spectrum one dominant tearing mode much higher than other secondary ones (quasi single helicity states). Tearing modes play crucial role determining energy and particle transport. Based on present understanding interplay between passive conductive...
Active feedback stabilization of multiple independent resistive wall modes is experimentally demonstrated in a reversed-field pinch plasma. A reproducible simultaneous suppression several nonresonant achieved. Coupling different due to the limited number coils observed agreement with theory. The RWMs also has an effect on tearing that are resonant central plasma, leading significant prolongation discharge pulse.
The resistive wall mode (RWM) and neoclassical tearing (NTM) have been simultaneously suppressed in the DIII-D for durations of over 2 s at beta values 20% above no-wall limit with modest electron cyclotron current drive very low plasma rotation. achieved rotation was significantly lower than reported previously. However, this regime where stable operation is obtained, it not unconditionally guaranteed. Various MHD activities, such as edge localized modes (ELMs) fishbones, begin to couple...
In this Letter, the linear stability of resistive wall modes (RWMs) in toroidal geometry for a reversed field pinch (RFP) plasma is studied. Three computational models are used: cylindrical code ETAW, MHD MARS-F, and CarMa code, able to take fully into account effects three-dimensional conducting structure which mimics real shell experimental device. The computed mode growth rates generally agree with data. features shell, like gaps, allow novel interpretation RWM spectrum RFP's remove its...
Two issues of the resistive wall mode (RWM) control code maturity are addressed: inclusion advanced damping physics beyond ideal MHD description, and possibility taking into account influence 3D features conducting structures on stability control. Examples formulations computational results given, using MARS-F/K codes CarMa code. The MARS-K calculations for a DIII-D plasma shows that fast ion contributions, which can give additional drift kinetic stabilization in perturbative approach, also...
Abstract The ASDEX Upgrade (AUG) programme, jointly run with the EUROfusion MST1 task force, continues to significantly enhance physics base of ITER and DEMO. Here, full tungsten wall is a key asset for extrapolating future devices. high overall heating power, flexible mix comprehensive diagnostic set allows studies ranging from mimicking scrape-off-layer divertor conditions DEMO at density fully non-inductive operation ( q 95 = 5.5, ) low density. Higher installed electron cyclotron...
Integrating the plasma core performance with an edge and scrape-off layer (SOL) that leads to tolerable heat particle loads on wall is a major challenge. The new European medium size tokamak task force (EU-MST) coordinates research ASDEX Upgrade (AUG), MAST TCV. This multi-machine approach within EU-MST, covering wide parameter range, instrumental progress in field, as ITER DEMO core/pedestal SOL parameters are not achievable simultaneously present day devices. A two prong adopted. On one...
Abstract Within the 9th European Framework programme, since 2021 EUROfusion is operating five tokamaks under auspices of a single Task Force called ‘Tokamak Exploitation’. The goal to benefit from complementary capabilities each machine in coordinated way and help developing scientific output scalable future largre machines. programme this ensures that ASDEX Upgrade, MAST-U, TCV, WEST JET (since 2022) work together achieve objectives Missions 1 2 Roadmap: i) demonstrate plasma scenarios...
Abstract Negative triangularity (NT) scenarios in TCV have been compared to positive (PT) using the same plasma shapes foreseen for divertor tokamak test operations. The experiments provided a NT/PT L-mode pair and PT H-mode with different heating mixes. Regardless of mix, NT L-modes always reached higher values pressure respect power recovered central heated up twice injected power. experimental analysis shows that this enhanced performance is due larger temperature density gradients close...
Abstract The paper presents experimental and modelling results of a comparison negative (NT) positive (PT) triangularity ASDEX Upgrade (AUG) discharges using the plasma shapes presently foreseen in DTT tokamak, under construction Italy. This work is part broader effort investigation to understand whether good properties observed NT scenarios DIII-D TCV may be extrapolated device more generally DEMO future operations. have shown practical gain running these AUG plasmas with only ECRH mixed...
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...
We describe plasma profiles evolution during pulsed poloidal current drive experiments performed with the RFX reversed field pinch device. With external of edge current, magnetic fluctuations are reduced suggesting a concomitant reduction spontaneous dynamo action. The electron temperature profile is seen to peak in core, consistently heat conductivity due substantial decrease MHD fluctuations. Our results also indicate that turbulence these fluctuations, which dominates transport core...