L. Balbinot
A5021650033- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Ionosphere and magnetosphere dynamics
- Particle accelerators and beam dynamics
- Nuclear reactor physics and engineering
- Plasma Diagnostics and Applications
- Gyrotron and Vacuum Electronics Research
- Physics of Superconductivity and Magnetism
- Electrostatic Discharge in Electronics
- Gas Dynamics and Kinetic Theory
- Atomic and Subatomic Physics Research
- Nuclear Materials and Properties
- Laser-Plasma Interactions and Diagnostics
Università degli Studi della Tuscia
2022-2024
National Agency for New Technologies, Energy and Sustainable Economic Development
2021
University of Padua
2017-2021
Abstract The JET 2019–2020 scientific and technological programme exploited the results of years concerted engineering work, including ITER-like wall (ILW: Be W divertor) installed in 2010, improved diagnostic capabilities now fully available, a major neutral beam injection upgrade providing record power 2019–2020, tested technical procedural preparation for safe operation with tritium. Research along three complementary axes yielded wealth new results. Firstly, plasma delivered scenarios...
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...
In its first phase of exploitation, JT-60SA will be equipped with an inertially cooled divertor, which can sustain heat loads 10 MW/m 2 on the targets for a few seconds, is much shorter than intended discharge duration. Therefore, in order to maximize duration discharges, it crucial develop operational scenarios high radiated fraction plasma edge region without unacceptably compromising scenario performance. this study, core and conditions unseeded neon-seeded deuterium H-mode were...
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>...
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...
This paper focuses on scrape-off layer and divertor modelling of the medium-density single-null scenario Divertor Test Tokamak facility (DTT), under construction in Italy.The was performed using 2D coupled fluid-Monte Carlo code SOLEDGE2D-EIRENE.For DTT pump designing, neutral pressure at aperture below dome is calculated deuterium-only cases as well with impurity seeding various puffing levels.This analysis also allowed characterization detachment influence pumping itself.Two different...
Abstract A large superconducting machine, JT-60SA has been constructed to provide major contributions the ITER program and DEMO design. For success of project fusion reactor, understanding development plasma controllability in relevant higher beta regimes are essential. focused on for scenario risk mitigation as well investigating regimes. This paper summarizes high research priorities strategy project. Recent works simulation studies prepare physics control experiments presented, such...
The main goal of the Divertor Tokamak Test facility (DTT) is to operate with a high value power-exhaust-relevant parameter PSOL/R in plasma scenarios similar those foreseen for Demonstration Fusion Power Plant (DEMO) terms low collisionality and neutral opacity. For these unique characteristics, accurate modelling principal scenario necessary machine designing. In edge numerical codes, cross-field transport profiles have impact on results. This work aims at providing coherent set parameters...
On the way to development of a fusion reactor based on Tokamak configuration, Divertor Test facility (DTT) [1] in construction Italy should provide useful information for DEMO [2] field power and particle exhaust. DTT is designed accept Single Null divertor (SND) also divertors optimized all present more promising configurations like Snowflake (SFD), X (XD), Super-X (SXD), X-point target (XPD) double null (DND). The DND particular has gained new attention as candidate considering its ability...
Abstract Divertor Tokamak Test Facility (DTT) is a new European superconducting tokamak, currently under final design, addressed to investigate alternative power exhaust solutions for DEMO. Although the divertor system not finalized yet, machine and port geometry set limitations on pumping operational space. A numerical study of neutral gas dynamics in region performed based DSMC method by applying DIVGAS code. The includes both single-null (SN) double-null (DN) configurations. For...
Abstract We use an integrated modeling workflow with the transport code ASTRA coupled quasi-linear model TGLF-SAT2, neoclassical NCLASS, FACIT for impurity and IMEP routines pedestal calculations, in order to predict evolution of plasma profiles Divertor Tokamak Test facility (DTT) tokamak main scenarios. The simulations cover whole confined radius, up separatrix, time including early phase limiter configuration, current ramp-up L-mode divertor L–H transition part stationary H-mode phase....
The deployment of neutral beam injectors in future fusion plants is beset by the particularly poor efficiency neutralization process. Beam-generated plasma neutralizers were proposed as a passive and intrinsically safe scheme efficient neutralizers. concept based on natural ionization gas target beam, suitable confinement secondary plasma. technological challenge such magnetic plasma: proof-of-principle for needed. possibility to test system small negative ion NIO1 discussed this paper....
Dispersion Interferometers (DI) present the fundamental advantage over conventional ones to be insensitive mechanical vibrations without requiring a second wavelength interferometer measure path length variations. On other hand, their optical setup requires duplication of nearly all components for any measuring chord. This makes realization multi-channel that is needed obtain density profiles via Abel inversion line integral measurements more complicated. To overcome such drawback DI, in...
The present paper shows the results of investigation about effects flux-expansion variation at inner strike point location on tungsten content in plasma core, and bulk radiation JET-ILW. divertor geometries have been designed using equilibrium code CREATE-NL. were experimentally achieved via a suitable optimization coils current few discharges with similar additional heating. Diagnostics used to examine: source from tiles both inter-ELM intra-ELM phases, profile shape inside total radiation....