R. Ambrosino
A5024778619- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Stability and Control of Uncertain Systems
- Particle accelerators and beam dynamics
- Nuclear reactor physics and engineering
- Advanced Control Systems Optimization
- Adaptive Control of Nonlinear Systems
- Control Systems and Identification
- Control and Stability of Dynamical Systems
- Fault Detection and Control Systems
- Ionosphere and magnetosphere dynamics
- Plasma Diagnostics and Applications
- Distributed Sensor Networks and Detection Algorithms
- Target Tracking and Data Fusion in Sensor Networks
- Energy Efficient Wireless Sensor Networks
- Guidance and Control Systems
- Distributed Control Multi-Agent Systems
- Advanced Differential Equations and Dynamical Systems
- Laser-Plasma Interactions and Diagnostics
- Nuclear Materials and Properties
- Neural Networks Stability and Synchronization
- Gene Regulatory Network Analysis
- Nuclear Physics and Applications
- Quantum chaos and dynamical systems
Parthenope University of Naples
2011-2025
University of Naples Federico II
2014-2024
Consorzio CREO (Italy)
2016-2024
University of Rome Tor Vergata
2024
Istituto Nazionale di Fisica Nucleare, Laboratori Nazionali di Frascati
2020-2023
National Agency for New Technologies, Energy and Sustainable Economic Development
2009-2023
Ingegneria dei Trasporti (Italy)
2018-2023
National Centre for Nuclear Research
2021
Royal Military Academy
2020
Fusion for Energy
2013-2016
Operation and exploitation of present future Tokamak reactors require advanced scenario modeling in order to optimize engineering parameters the design phase as well physics performance during phase. The simulation scenarios involves simultaneous different regions reactor, characterized by symmetries, predict quantities such particle energy confinement, fusion yield, power deposited on wall, wall load from fast particles. JINTRAC is a system 25 interfaced Tokamak-physics codes for integrated...
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...
As part of the ITER Design Review and in response to issues identified by Science Technology Advisory Committee, physics requirements were reviewed as appropriate updated. The focus this paper will be on recent work affecting design with special emphasis topics near-term procurement arrangements. This describe results on: sensitivity studies, poloidal field coil requirements, vertical stability, effect toroidal ripple thermal confinement, material choice heat load for plasma-facing...
The 2014–2016 JET results are reviewed in the light of their significance for optimising ITER research plan active and non-active operation. More than 60 h plasma operation with first wall materials successfully took place since its installation 2011. New multi-machine scaling type I-ELM divertor energy flux density to is supported by principle modelling. relevant disruption experiments modelling reported a set three mitigation valves mimicking setup. Insights L–H power threshold Deuterium...
The finite-time stability problem for state-dependent impulsive dynamical linear systems (SD-IDLS) is addressed in this note. SD-IDLS are a special class of hybrid which exhibit jumps when the state trajectory reaches <i xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">resetting</i> xmlns:xlink="http://www.w3.org/1999/xlink">set</i> . A sufficient condition provided. xmlns:xlink="http://www.w3.org/1999/xlink">S</i> -procedure arguments exploited to...
In the European fusion roadmap, ITER is followed by a demonstration power reactor (DEMO), for which conceptual design under development. This paper reports first results of coherent effort to develop relevant physics knowledge that (DEMO Physics Basis), carried out experts. The program currently includes investigations in areas scenario modeling, transport, MHD, heating & current drive, fast particles, plasma wall interaction and disruptions.
Abstract For the past several years, JET scientific programme (Pamela et al 2007 Fusion Eng. Des . 82 590) has been engaged in a multi-campaign effort, including experiments D, H and T, leading up to 2020 first with 50%/50% D–T mixtures since 1997 ever plasmas ITER mix of plasma-facing component materials. this purpose, concerted physics technology was launched view prepare campaign (DTE2). This paper addresses key elements developed by directly contributing preparation. intense preparation...
The plasma diagnostic and control (D&C) system for a future tokamak demonstration fusion reactor (DEMO) will have to provide reliable operation near technical physics limits, while its front-end components be subject strong adverse effects within the nuclear high temperature environment. ongoing developments ITER D&C represent an important starting point progressing towards DEMO. Requirements detailed exploration of are however pushing design using sophisticated methods aiming large spatial...
For several reasons the challenge to keep loads first wall within engineering limits is substantially higher in DEMO compared ITER. Therefore pre-conceptual design development for that currently ongoing Europe needs be based on load estimates are derived employing most recent plasma edge physics knowledge.
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...
This work presents an overview of the integrated strategy developed, as part DEMO Key Design Integration Issue 1 (KDII1), to protect EU-DEMO first wall (FW) from planned and unplanned plasma transients by employing discrete limiters. The present Breeding Blanket (BB) FW design, which aims at minimizing loss neutrons while travelling breeding zone, is able withstand steady state heat fluxes up ≈1-1.5 MW/m² [1], not sufficient guarantee its integrity for most plasma-FW direct contact....
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">...
The objective of thermonuclear fusion consists producing electricity from the coalescence light nuclei in high temperature plasmas. most promising route to envisages confinement such plasmas with magnetic fields, whose studied configuration is tokamak. Disruptions are catastrophic collapses affecting all tokamak devices and one main potential showstoppers on a commercial reactor. In this work we report how, deploying innovative analysis methods thousands JET experiments covering isotopic...
Abstract Robust finite‐time stability (FTS) for a class of uncertain hybrid systems is tackled the first time in this paper. In particular, impulsive dynamical linear (U‐IDLS) are considered. U‐IDLS exhibit jumps state trajectory that can be either time‐driven (time‐dependent IDLS) or driven by specific values (state‐dependent IDLS). Furthermore, may uncertainties both dynamic and jump equation. paper, sufficient conditions FTS IDLS provided. These results require solution feasibility...
Self-consistent transport simulation of ITER scenarios is a very important tool for the exploration operational space and scenario optimisation. It also provides an assessment compatibility developed (which include fast transient events) with machine constraints, in particular poloidal field (PF) coil system, heating current drive (H&CD), fuelling particle energy exhaust systems. This paper discusses results predictive modelling all reference variants using two suite linked equilibrium...