C. Marchetto

ORCID: 0000-0002-7920-2873
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Research Areas
  • Magnetic confinement fusion research
  • Fusion materials and technologies
  • Ionosphere and magnetosphere dynamics
  • Superconducting Materials and Applications
  • Laser-Plasma Interactions and Diagnostics
  • Nuclear reactor physics and engineering
  • Particle accelerators and beam dynamics
  • Plasma Diagnostics and Applications
  • Nuclear Physics and Applications
  • Nuclear Materials and Properties
  • Electrostatic Discharge in Electronics
  • Chaos control and synchronization
  • Anomaly Detection Techniques and Applications
  • Atomic and Subatomic Physics Research
  • Advanced Sensor Technologies Research
  • Advancements in Semiconductor Devices and Circuit Design
  • Solar and Space Plasma Dynamics
  • Dust and Plasma Wave Phenomena
  • High-pressure geophysics and materials
  • High-Energy Particle Collisions Research
  • Quantum chaos and dynamical systems
  • Fault Detection and Control Systems

National Agency for New Technologies, Energy and Sustainable Economic Development
2009-2025

Polytechnic University of Turin
2021-2025

Institute for Complex Systems
2022-2024

Culham Science Centre
2014-2024

Culham Centre for Fusion Energy
2024

Institute for the Science and Technology of Plasmas
2022

Royal Military Academy
2020

Institute of Plasma Physics
2005-2019

Cineca
2005

University of Milan
2003

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...

10.1585/pfr.9.3403023 article EN Plasma and Fusion Research 2014-01-01

The replacement of the JET carbon wall (C-wall) by a Be/W ITER-like (ILW) has affected plasma energy confinement. To investigate this, experiments have been performed with both C-wall and ILW to vary heating power over wide range for plasmas different shapes.

10.1088/0029-5515/55/5/053031 article EN Nuclear Fusion 2015-04-23

The resilience to chaotic perturbations of one-parameter one-degree-of-freedom Hamiltonian dynamics is shown increase when its corresponding separatrix vanishes due a saddle-node bifurcation. This first highlighted for the magnetic chaos related quasisingle helicity (QSH) states reversed field pinch. It provides rationale confinement improvement helical structures experimentally found QSH plasmas; such feature would not be expected from classical resonance overlap picture as disappearance...

10.1103/physrevlett.85.3169 article EN Physical Review Letters 2000-10-09

Since the 2012 IAEA-FEC Conference, FTU operations have been largely devoted to runaway electrons generation and control, exploitation of 140 GHz electron cyclotron (EC) system liquid metal limiter elements. Experiments on shown that measured threshold electric field for their is larger than predicted by collisional theory can be justified considering synchrotron radiation losses. A new control algorithm was developed tested in presence a current plateau, allowing minimize interactions with...

10.1088/0029-5515/55/10/104005 article EN cc-by Nuclear Fusion 2015-03-27

In Hybrid plasma operation in JET with its ITER-like wall (JET-ILW) it is found that n>1 tearing activity can significantly enhance the rate of on-axis peaking tungsten impurities, which turn degrades discharge performance. Core n=1 instabilities be beneficial removing impurities from core (e.g. sawteeth or fishbones), but conversely also degrade confinement (particularly combination simultaneous n=3 activity). The nature MHD discharges, both previous Carbon and subsequent JET-ILW, surveyed...

10.1088/0029-5515/56/6/066002 article EN Nuclear Fusion 2016-04-27

The EDGE2D-EIRENE code is applied for simulation of divertor detachment during matched density ramp experiments in high triangularity, L-mode plasmas both JET-Carbon (JET-C) and JET-ITER-Like Wall (JET-ILW). runs without drifts includes either C or Be as impurity, but not W, assuming that the W targets have been coated with via main chamber migration. simulations reproduce reasonably well observed particle flux raised JET-C JET-ILW can better match experimental in-out target power asymmetry...

10.1088/0029-5515/54/9/093012 article EN Nuclear Fusion 2014-08-19

Abstract In high confinement mode, highly shaped plasmas with edge localized modes in JET, and for heating power of 15–17 MW, the fluid code EDGE2D-EIRENE predicts transition to detachment assisted by nitrogen at low field side (LFS) target when more than 50% crossing separatrix between ELMs is radiated divertor chamber, i.e. ~4 MW. This observed both ITER-like wall (JET-ILW) carbon (JET-C) configurations consistent experimental observations within their uncertainty. these conditions, peak...

10.1088/0029-5515/56/4/046012 article EN Nuclear Fusion 2016-03-16

We provide numerical evidence of the role finite Larmor radius effects in nonlinear dynamics magnetic field line reconnection high-temperature, strong guide plasmas a slab configuration, large Δ' regime. Both ion and electron temperature introduce internal energy variations related to mechanical compression terms balance, thus contributing regularize gradients density with respect cold regimes. For values radii that are not asymptotically small, two no longer interchangeable, contrast what...

10.1088/0741-3335/53/3/035008 article EN Plasma Physics and Controlled Fusion 2011-01-28

The biorthogonal decomposition analysis of signals from an array Mirnov coils is able to provide the spatial structure and temporal evolution magnetohydrodynamic (MHD) instabilities in a tokamak. Such can be adapted data acquisition elaboration system suitable for fast real time applications such as instability detection disruption precursory markers computation. This paper deals with description this technique applied Frascati Tokamak Upgrade (FTU).

10.1088/0741-3335/56/11/114012 article EN Plasma Physics and Controlled Fusion 2014-10-17

The linear stability of the tearing mode (TM) in a plasma column is investigated presence viscosity and finite equilibrium current density gradients (i.e., asymmetries). It shown that for low β, both effects are essential order to properly describe behaviour close marginality. In particular, theory introduces critical threshold destabilization, such perturbation grows only if Δ′>Δ′cr. value Δ′cr depends on configuration parameters. Most importantly, can take negative values, thus...

10.1063/1.3660410 article EN Physics of Plasmas 2011-11-01

Abstract Self-healing liquid metal divertors (LMDs) based on the Capillary Porous Structure (CPS) concept are currently being considered among possible solutions to power exhaust problem in future fusion reactors. Indeed, passive replenishment of plasma-facing surface by capillary forces and self-shielding target via vapor emission can potentially improve divertor lifetime its resilience transient loads. On other hand, LMD erosion be significant due evaporation thermal sputtering, top...

10.1007/s10894-023-00377-5 article EN cc-by Journal of Fusion Energy 2023-08-23

To perform real time plasma control experiments using EC heating waves by the new fast launcher installed on FTU a dedicated data acquisition and elaboration system has been designed recently. A prototypical version of acquisition/control recently developed will be tested machine in its next experimental campaign. The open-source framework MARTe (Multi-threaded Application Real-Time executor) Linux/RTAI real-time operating chosen as software platform to realize system. Standard...

10.1051/epjconf/20123204015 article EN cc-by EPJ Web of Conferences 2012-01-01

Experiments on real time control of magneto-hydrodynamic (MHD) instabilities using injection electron cyclotron waves (ECW) are being performed with a system based only three key items: an equilibrium estimator statistical regression, MHD instability marker (SVDH) three-dimensional array pick-up coils and fast ECW launcher able to poloidally steer the EC absorption volume dρ/dt = 0.1/30 ms maximum radial speed. The instability, usually tearing mode poloidal number m toroidal n such that m/n...

10.1088/0029-5515/55/8/083010 article EN Nuclear Fusion 2015-07-01

The automatic controller developed for MHD instability control on FTU via the real time (RT) EC launcher [1, 2] is based a-priori estimate of instabilities location and fast elaboration stream diagnostic data. A data acquisition system, existing standard diagnostics, collects thermal magnetic signals by a 12-channels ECE polychromator [3] set 22 Mirnov coils respectively. Moreover, waveform from directional couplers along transmission line acquired as well. This processed in timescale...

10.1051/epjconf/20123202015 article EN cc-by EPJ Web of Conferences 2012-01-01

A Real-Time system for the data acquisition and processing in order to control magnetohydrodynamics instabilities tokamak is presented. It based on both a-priori information derived from statistical treatment of a database live measurements plasma elaborated by diagnostic codes executed at different sampling frequencies accordingly estimated signals bandwidth (0.01ms 1ms). The actuator 2×0.4MW, 140GHz ECRH equipped with fast quasi-optical steerable launcher.

10.1109/cdc.2012.6426376 article EN 2012-12-01

Since the 2010 IAEA-FEC Conference, FTU has exploited improvements in cleaning procedures and density control system to complete a systematic exploration of access high-density conditions wide range plasma currents magnetic fields. The line-averaged densities at disruptive limit increased more than linearly with toroidal field, while no dependence on current was found; fact, maximum 4.3 × 1020 m−3 reached B = 8 T even minimum 0.5 MA, corresponding twice Greenwald limit. lack due increase...

10.1088/0029-5515/53/10/104012 article EN Nuclear Fusion 2013-09-26

Views Icon Article contents Figures & tables Video Audio Supplementary Data Peer Review Share Twitter Facebook Reddit LinkedIn Tools Reprints and Permissions Cite Search Site Citation C. Marchetto, F. Gandini, S. Cirant, G. Granucci, E. Lazzaro, B. Esposito; MHD Structure Analysis by Singular Value Decomposition as a Tool for ECRH RT‐Control of Instabilities on FTU. AIP Conference Proceedings 26 November 2009; 1187 (1): 519–522. https://doi.org/10.1063/1.3273804 Download citation file: Ris...

10.1063/1.3273804 article EN AIP conference proceedings 2009-01-01

The Real-Time system for the control of magnetohydrodynamics instabilities in FTU tokamak is presented. It based on both a-priori information derived from statistical treatment a database and elaboration live diagnostics data. analysis codes are executed different time threads multi-processors machines. actuator 2×0.4MW 140 GHz ECRH equipped with new fast quasi-optical steerable launcher.

10.1051/epjconf/20123202003 article EN cc-by EPJ Web of Conferences 2012-01-01

The generation of a coherent ion flow due to the injection in plasma purely electrostatic wave finite amplitude, propagating at right angle with ambient uniform magnetic field, is investigated making use kinetic code which solves fully nonlinear Vlasov equations for electrons and ions, coupled Maxwell equations, one spatial two velocity dimensions. A uniformly magnetized slab considered. frequency assumed range fourth harmonic cyclotron frequency, vector chosen order model propagation an...

10.1103/physreve.67.026405 article EN Physical review. E, Statistical physics, plasmas, fluids, and related interdisciplinary topics 2003-02-07

Various active control strategies of the Neoclassical tearing modes are being studied in present tokamaks using established detection techniques which exploit measurements fluctuations magnetic field and electron temperature. The extrapolation such to fusion reactor scale is made problematic by neutron fluence physics conditions related high plasma temperature density degrade spatial resolution measurements.

10.1063/1.4894021 article EN AIP conference proceedings 2014-01-01
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