G. Ambrosino
- Magnetic confinement fusion research
- Superconducting Materials and Applications
- Fusion materials and technologies
- Particle accelerators and beam dynamics
- Nuclear reactor physics and engineering
- Plasma Diagnostics and Applications
- Adaptive Control of Nonlinear Systems
- Ionosphere and magnetosphere dynamics
- Advanced Control Systems Optimization
- Water resources management and optimization
- Power System Optimization and Stability
- Iterative Learning Control Systems
- Fault Detection and Control Systems
- Stability and Control of Uncertain Systems
- Stability and Controllability of Differential Equations
- Structural Load-Bearing Analysis
- Seismic Performance and Analysis
- Dynamics and Control of Mechanical Systems
- Gas Dynamics and Kinetic Theory
- Robotic Mechanisms and Dynamics
- Frequency Control in Power Systems
- Smart Grid Security and Resilience
- Non-Destructive Testing Techniques
- Laser-Plasma Interactions and Diagnostics
- Advanced Data Storage Technologies
Consorzio CREO (Italy)
2007-2024
Royal Military Academy
2020
Center for Research and Telecommunication Experimentation for Networked Communities
2020
University of Naples Federico II
2008-2017
Ingegneria dei Trasporti (Italy)
1993-2017
Fusion for Energy
2016
ITER
2016
Parthenope University of Naples
2016
National Agency for New Technologies, Energy and Sustainable Economic Development
2004-2014
Istituto Nazionale di Fisica Nucleare, Sezione di Napoli
1986-2014
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...
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...
Model reference adaptive controllers, when only input and output measurements are available, designed using the theory of variable structure systems. State filters used in order to obtain differentiator-free controllers. The proposed design allows error transient be prescribed advance. drawbacks deriving from typical high-frequency chattering control signal during sliding motion can partially eliminated by means a little modification adaptation law that does not cause deteriorate considerably.
In this brief, we consider the problem of 3-D path generation and tracking for unmanned air vehicles (UAVs). The proposed algorithm allows us to find a satisfying arbitrary initial final conditions, specified in terms position velocity. Our method assumes that aircraft structural dynamic limitations can be translated turn radius constraint; therefore, generated paths satisfy constraint on minimum admissible turning radius. guarantees, under assumptions, error, both attitude, asymptotically...
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...
We propose a new model-following control scheme for class of nonlinear plants. The feedback signal is continuous function all its arguments. It shown that this guarantees tracking error remains bounded and tends to neighborhood the origin with rate not inferior an exponential one; furthermore, it allows designer arbitrarily prescribe convergence size set ultimate boundedness.
This paper summarises the results of a numerical study on non linear response steel concentric braced frames under monotonic and cyclic loads, using force-based finite elements with section fibre discretisation. The first part is addressed to analyse single brace response. A parametric analysis was carried out discussed evaluate accuracy model, examining influence initial camber, material modelling, type element, number integration points fibers. second concerned modelling issues whole...
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...
Plasma current, position and shape control systems modeling approaches were reviewed. The literature was divided into three categories, namely plasma radial current control, vertical stabilization of elongated plasmas, control. problem can be easily solved using a filament model - the Shafarov lumped parameter equation two separate PID controllers. At most, MIMO controller used if decoupling is desired. Stabilization motion requires new strategies in which algorithm changed on basis an...
FAST is a new machine proposed to support ITER experimental exploitation as well anticipate DEMO relevant physics and technology. aimed at studying, under burning plasma conditions, fast particle (FP) physics, operations wall interaction in an integrated way. has the capability approach all scenarios significantly closer than present day experiments using deuterium plasmas. The necessity of achieving performance with moderate cost led conceiving compact tokamak (R = 1.82m, 0.64m) high...
In physical theory models, the hysteretic response of concentric braces is simulated by modelling bracings with two nonlinear fibre-section beam–column elements connected together an initial out-of-straightness imperfection (∆0). The width such parameter governing numerical prediction brace buckling. this paper, accuracy different formulations ∆0 investigated and validated against monotonic cyclic experimental results from literature carried out on bracing configurations. Correlations...
The poloidal field (PF) coil system on ITER, which provides both feedforward and feedback control of plasma position, shape, current, is a critical element for achieving mission performance. Analysis PF capabilities has focused the 15 MA Q = 10 scenario with 300–500 s flattop burn phase. operating space available ELMy H-mode discharges in ITER upgrades to coils or associated systems establish confidence that objectives can be reached have been identified. Time dependent self-consistent...
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...
ITER plasma control design solutions and performance requirements are strongly driven by its nuclear mission, aggressive commissioning constraints, limited number of operational discharges. In addition, high energy content, heat fluxes, neutron very long pulse operation place novel demands on in many areas ranging from boundary divertor regulation to kinetics stability control. Both experimental operations schedules provide time for tuning algorithms relative operating devices. Although...
Self-consistent computations are carried out to study the stability of resistive wall mode (RWM) in DIII-D [J. L. Luxon, Nucl. Fusion 42, 614 (2002)] plasmas with slow plasma rotation, using hybrid kinetic-magnetohydrodynamic code MARS-K [Y. Q. Liu et al., Phys. Plasmas 15, 112503 (2008)]. Based on kinetic resonances between and thermal particle toroidal precession drifts, self-consistent modeling predicts less stabilization compared perturbative approaches, experiments. A simple analytic...
The international thermonuclear experimental reactor (ITER) is the next step toward realization of electricity-producing fusion power plants. ITER has been designed so as to reach plasma burning condition, and operate with high elongated unstable plasmas. However, due constraints which affect machine realization, these open-loop performance plasmas can be hardly stabilized using Poloidal Field coils placed outside tokamak vessel. In this paper, it proposed use in-vessel vertically stabilize...
In this paper, we consider the problem of 3D path generation and tracking for unmanned air vehicles (UAVs). The proposed algorithm allows us to find a satisfying arbitrary initial final conditions, specified in terms position velocity. Our method assumes that most aircraft structural dynamic limitations can be translated turn radius constraint; therefore, generated paths satisfy constraint on minimum admissible turning radius. guarantees, under assumptions, error, both attitude,...
An overview of the preliminary design ITER plasma control system (PCS) is described here, which focusses on needs for 1st and early operation in hydrogen/helium (H/He) up to a current 15 MA with moderate auxiliary heating power low confinement mode (L-mode). Candidate schemes basic magnetic control, including divertor kinetic electron density gas puffing pellet injection, were developed. Commissioning systems included as well support functions stray field topology real-time boundary...
The ITER plasma control system (PCS) has successfully completed its final design for the first (FP) and engineering operations (EOs) phase plant commissioning begun as prepares this operation phase. Commissioning of essential systems will continue each is made ready operation. Tokamak assembly with base lower cylinder cryostat most poloidal field (PF) coil installed in tokamak pit. vacuum vessel (VV) sector accompanying two toroidal (TF) coils are being prepared transfer to Once assembled,...
This paper describes a set of graphic tools for the design and validation new plasma shape controller [eXtreme Shape Controller (XSC)], which has been recently implemented at Joint European Torus tokamak. The XSC enables operation with high elongation triangularity plasmas. software suite, is called Tools, developed to automate procedure XSC. These make use user interfaces allow nonspecialist users prepare operative scenarios, without help from modeling control specialists. Once generated,...
P-EFIT, a GPU parallel equilibrium reconstruction code, is based on the EFIT framework, but built with CUDA™ (Compute Unified Device Architecture) to take advantage of massively Graphical Processing Unit (GPU) cores significantly accelerate computation. With parallelized Grad-Shafranov solver and middle-scale matrix calculation modules, P-EFIT can accurately reproduce algorithms at fraction computational time. Integrated into EAST plasma control system, not only provides signal results also...