A5002056153- Magnetic confinement fusion research
- Fusion materials and technologies
- Particle accelerators and beam dynamics
- Superconducting Materials and Applications
- Ionosphere and magnetosphere dynamics
- Nuclear reactor physics and engineering
- Laser-Plasma Interactions and Diagnostics
- Plasma Diagnostics and Applications
- High-Energy Particle Collisions Research
- Solar and Space Plasma Dynamics
- Metal and Thin Film Mechanics
- Ion-surface interactions and analysis
- Atomic and Molecular Physics
- Nuclear Materials and Properties
- Fault Detection and Control Systems
- Fluid Dynamics and Turbulent Flows
- Computational Fluid Dynamics and Aerodynamics
- Nuclear Physics and Applications
- Wind and Air Flow Studies
- Turbomachinery Performance and Optimization
- Viral Infections and Vectors
- Mass Spectrometry Techniques and Applications
- GNSS positioning and interference
- Meteorological Phenomena and Simulations
- Anomaly Detection Techniques and Applications
Institute for the Science and Technology of Plasmas
2023-2024
National Agency for New Technologies, Energy and Sustainable Economic Development
2015-2024
University of Padua
2015-2024
Max Planck Institute for Plasma Physics
2024
Istituto Nazionale di Fisica Nucleare
2024
National Research Council
2017-2022
Royal Military Academy
2020
Institute of Plasma Physics
2017
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...
The European DEMO is a pulsed device with pulse length of 2 hours. functions devoted to the heating and current drive system are: plasma breakdown, ramp-up flat-top where fusion reactions occur, control during phase, finally ramp-down. EU-DEMO project was in Pre-Concept Design Phase 2014-2020, meaning that some cases, design values precise requirements from physics point view were not yet frozen. A total 130 MW considered for all phases plasma: flat top, 30 required neoclassical tearing...
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...
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 We present an overview of results from a series L–H transition experiments undertaken at JET since the installation ITER-like-wall (JET-ILW), with beryllium wall tiles and tungsten divertor. Tritium, helium deuterium plasmas have been investigated. Initial in tritium show ohmic transitions low density power threshold for ( P LH ) is lower than ones densities, while we still lack contrasted data to provide scaling high densities. In there notable shift which minimum <?CDATA...
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 The recent deuterium–tritium campaign in JET-ILW (DTE2) has provided a unique opportunity to study the isotope dependence of L-H power threshold an ITER-like wall environment (Be and W divertor). Here we present results from dedicated transition experiments at JET-ILW, documenting tritium plasmas, comparing them with matching deuterium hydrogen datasets. From earlier it is known that as plasma isotopic composition changes deuterium, through varying deuterium/hydrogen concentrations,...
Abstract This paper explores the operational boundaries and power availability of neutral beam injection (NBI) system in ITER, with a specific focus on shine-through loss prevention. Shine-through, phenomenon where part injected remains un-ionized plasma directly impacts first wall components, poses significant risk to lifetime ITER’s plasma-facing components. The window for NBI is consequently constrained by these losses, which are influenced factors such as density, energy, geometry....
Abstract This paper reviews recent experimental advances in characterising the low-to-high confinement mode (L-H) transition tokamaks, with a particular focus on ITER-relevant results from JET and metallic wall tokamaks. Achieving H-mode is critical for success of ITER, robustness access recently revised ITER research plan assessed present paper. Findings machines are applied to predictions both early nuclear operational phases. Notably, new multi-machine, wall-specific scaling L-H power...
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...
The integrated transport analysis suite, TASK3D-a (Analysis), has been developed to be capable for routine whole-discharge analyses of plasmas confined in three-dimensional (3D) magnetic configurations such as the LHD. dynamic energy balance NBI-heated was made possible first version released September 2012. suite further extended through implementing additional modules neoclassical and ECH deposition 3D configurations. A module also added creating systematic data International...
This work presents an upgrade of the FIT3D neutral beam–plasma interaction code, part TASK3D, a transport suite codes, and its application to LHD experiments in framework preparation for first deuterium LHD. The beam injector (NBI) system will be upgraded D injection, efforts have been recently made extend modelling capabilities operations. implemented upgrades enable NBI plasmas are presented, with discussion benchmark models used. In particular, ionization module has modified routine...
Plasma fuelling and density control are an open issue regarding EU DEMO studies solutions may be different from present day experiments. The paper addresses through JINTRAC core transport code simulations the feasibility of methods such as gas puff pellet injection influence neoclassical anomalous inward pinch in edge barrier order to achieve target density. Given expected high fusion power production, He accumulation plasma is a critical issue, estimation impurities (He, Ar, W) on dilution...
The pre-conceptual design for a European pulsed fusion reactor (DEMO1) is ongoing and one of the most challenging activities within scenario modeling studies deals with numerical investigations DEMO1 transient phases. This paper presents an investigation on both ramp-up ramp-down phases by selected plasma trajectories. Plasma evolution has clear impact engineering reactor, e.g. auxiliary power systems, current ramp-rates requirements coil system. Studies have been carried out fast tokamak...
Heating and current drive (H&CD) systems are being investigated for a demonstration fusion power plant DEMO to deliver net electricity the grid around 2050. Compared ITER, which has show generation of 500-MW thermal power, target is successful production 300 500 MW electrical aim self-sufficient tritium fuel cycle. Three H&CD under development in Europe, electron cyclotron (EC) system, neutral beam injection (NBI) ion system. Based on present studies plasma ramp-up, ramp-down, flat top...
In this paper we analyze fast ion motion in the divertor tokamak test (DTT) device (Albanese et al 2017 Nucl. Fusion 57 016010). It is planned that DTT will be heated through a mix of 45 MW heating power, including 15 negative-ion-based neutral beam (NNBI) which currently being developed by Consorzio RFX Padova, Italy (Agostinetti 2019 Eng. Design 146 441–446). An issue for toroidal field (TF) ripple with maximum value about ∼0.42% (with respect to on-axis magnetic B0) expected on low-field...
Abstract The understanding of the physics underlying L-H transition has strong implications for ITER experimental reactor and demonstration power plant (DEMO). In many tokamaks, including JET, it been observed that, at a particular plasma density, n e,min , necessary to access H-mode P is minimum. present work, transitions JET deuterium plasmas heated by neutral beam injection (NBI) are studied first time means balance analysis characterize main contributions in transition, through...
In this study we are investigating the physics of ICRH plasma interaction in Divertor Tokamak Test (DTT) facility, on basis and tokamak parameters characterizing machine, as well antenna design. An assessment scenarios which involves i) frequency choice, ii) power spectrum, iii) minority H and/or 3He heating, iv) Deuterium 2nd harmonic v) fast particles energies, has been carried out. Well assessed numerical tools have used for solution relevant electromagnetic wave equation coupled to...