A5051180513- Magnetic confinement fusion research
- Superconducting Materials and Applications
- Fusion materials and technologies
- Particle accelerators and beam dynamics
- Ionosphere and magnetosphere dynamics
- Laser-Plasma Interactions and Diagnostics
- Physics of Superconductivity and Magnetism
- Nuclear reactor physics and engineering
- Meteorological Phenomena and Simulations
- HVDC Systems and Fault Protection
- Atomic and Subatomic Physics Research
- Nuclear Physics and Applications
- Diverse academic and cultural studies
National Agency for New Technologies, Energy and Sustainable Economic Development
2019-2024
ENEA Frascati Research Centre
2023-2024
Istituto Nazionale di Fisica Nucleare, Laboratori Nazionali di Frascati
2023-2024
Università degli Studi della Tuscia
2022
Consorzio CREO (Italy)
2017-2022
University of Naples Federico II
2016-2020
Ingegneria dei Trasporti (Italy)
2017-2019
Parthenope University of Naples
2019
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...
Plasma exhaust has been identified as a major challenge towards the realisation of magnetic confinement fusion. To mitigate risk that single null divertor (SND) with high radiation fraction in scrape-of-layer (SOL) adopted for ITER will not extrapolate to DEMO reactor, EUROfusion consortium is assessing potential benefits and engineering challenges alternative configurations. Alternative configurations could be readily design include X (XD), Super-X (SXD), Snowflake (SFD) double (DND). The...
Abstract Plasmas with negative triangularity (NT) shape have been recently shown to be able achieve H-mode levels of confinement in L-mode, avoiding detrimental edge localised modes. Therefore, this plasma geometry is now studied as a possible viable option for future fusion reactor. Within framework, an NT under investigation the full power scenario Divertor Tokamak Test (DTT) facility, construction Italy, <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll">...
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...
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 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...
A ITER-like vertical stabilization (VS) algorithm has been successfully deployed and commissioned at EAST. The proposed decouples the VS from plasma shape control, while algorithms previously implemented to stabilize EAST exhibit a strong coupling with control system. As consequence, prevent deployment of advanced multi-input-multi-output (MIMO) schemes, such as ones in Albanese et al 2016 (Proc. IEEE Multi-Conf. System Control (Buenos Aires, Argentina) pp 611–6) Kolemen (2015 J. Nucl....
In the field of nuclear fusion, power exhaust problem is still an open issue and represents one biggest problems for realization a commercial fusion plant. According to “European Fusion Roadmap”, dedicated facility able investigate possible solutions heat mandatory. For this purpose, mission Divertor Tokamak Test (DTT) tokamak study different divertor. This paper presents plasma scenarios standard alternative configurations in DTT. The Single Null scenario described detail. are also...
Abstract Experiments, gyrokinetic simulations and transport predictions were performed to investigate if a negative triangularity (NT) L-mode option for the Divertor Tokamak Test (DTT) full-power scenario would perform similarly positive (PT) H-mode reference scenario, avoiding harmful edge localized modes (ELMs). The show that beneficial effect of NT coming from edge/scrape-off layer (SOL) region <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:mrow>...
This paper deals with the magnetic control system of EAST tokamak, i.e. in charge controlling position and shape plasma column into vacuum vessel, as well current that flows it. A multi-input multi-output architecture is proposed order to achieve integrated both boundary flux expansion scrape-off layer. The based on an XSC-like approach [1]. In show effectiveness approach, a set Matlab/Simulink <sup xmlns:mml="http://www.w3.org/1998/Math/MathML"...
One of the main challenges concerning next generation tokamaks (such as DEMO) will be development a heat and power exhaust system able to withstand large loads expected in divertor region. A dedicated Divertor Tokamak Test (DTT) facility has been proposed EUROfusion Roadmap, with aim testing unconventional solutions, such advanced magnetic configurations liquid metal divertors. Magnetic control alternative plasma configurations, X-Divertor, play key role solution yet can challenging point,...