G. Ambrosino

ORCID: 0000-0002-2549-2772
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About
Contact & Profiles
Research Areas
  • 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...

10.1088/1741-4326/ac47b4 article EN cc-by Nuclear Fusion 2022-01-04

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...

10.1088/1741-4326/aa5e28 article EN cc-by Nuclear Fusion 2017-06-15

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.

10.1080/00207178408933250 article EN International Journal of Control 1984-06-01

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...

10.1109/tcst.2009.2014359 article EN IEEE Transactions on Control Systems Technology 2009-06-25

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...

10.1088/1741-4326/ab2276 article EN cc-by Nuclear Fusion 2019-05-17

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.

10.1109/tac.1985.1103929 article EN IEEE Transactions on Automatic Control 1985-03-01

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...

10.12989/scs.2013.15.5.539 article EN Steel and Composite Structures 2013-11-25

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...

10.1038/s41467-024-46242-7 article EN cc-by Nature Communications 2024-03-18

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...

10.1109/mcs.2005.1512797 article EN IEEE Control Systems 2005-09-26

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...

10.1088/0029-5515/50/9/095005 article EN Nuclear Fusion 2010-07-30

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...

10.1002/tal.1160 article EN The Structural Design of Tall and Special Buildings 2014-04-20

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...

10.1088/0029-5515/49/8/085034 article EN Nuclear Fusion 2009-07-28

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...

10.1088/0741-3335/52/10/104002 article EN Plasma Physics and Controlled Fusion 2010-09-07

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...

10.1063/1.4907901 article EN Physics of Plasmas 2015-02-01

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...

10.1063/1.3123388 article EN Physics of Plasmas 2009-04-29

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...

10.1109/tcst.2010.2042601 article EN IEEE Transactions on Control Systems Technology 2010-03-12

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,...

10.1109/cdc.2006.377555 article EN 2006-01-01

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...

10.1088/1741-4326/aa8177 article EN Nuclear Fusion 2017-07-23

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,...

10.1088/1741-4326/ac2339 article EN Nuclear Fusion 2021-09-02

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,...

10.1109/tps.2007.896989 article EN IEEE Transactions on Plasma Science 2007-06-01

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...

10.1088/1741-4326/ab91f8 article EN Nuclear Fusion 2020-05-11
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