Federico Alberto Alfredo Felici

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An optimized plasma current ramp-down strategy is critical for safe and fast termination of plasma discharges in a tokamak demonstration fusion reactor (DEMO), both in planned and emergency scenarios, avoiding plasma disruptions and excessive heat loads to ...

The paper details the process of developing the ITER Plasma Control System (PCS), that is, how to design and deploy it systematically, in the most efficient and effective manner. The integrated nature of the ITER PCS, with its multitude of coupled control ...

The ITER ECRH upper launcher (UL) uses a steering mechanism assembly (SMA) to steer the beams in the appropriate location for controlling magnetohydrodynamic (MILD) activity in the plasma (NTMs and sawtooth oscillations). ...

For long-pulse tokamaks, one of the main challenges in the control strategy is to simultaneously reach multiple control objectives and to robustly handle in real-time (RT) unexpected events [off-normal-events (ONEs)] with a limited set of actuators. We hav ...

Plasma start-up is typically achieved manipulating poloidal magnetic fields, gas injection and possibly auxiliary heating. Model-based design techniques have been gaining increasing attention in view of future large tokamaks which have more stringent const ...

On the basis of several recent breakthroughs in fusion research, many activities have been launched around the world to develop fusion power plants on the fastest possible time scale. In this context, high-fidelity simulations of the plasma behavior on lar ...

Electron cyclotron heating (ECH) is widely used in magnetic fusion devices, and the polarization of the injected millimeter-wave beams plays a crucial role in the propagation and absorption of the beam energy by the plasma. This polarization can be adjuste ...

The polarization of ECRH waves, set by the orientation of a pair of corrugated mirror polarizers in the transmission line, determines the degree of coupling to O- and X-modes in the plasma and has an important effect on the first-pass absorption. Existing ...

In the standard scenario of tokamak plasma operation, sawtooth crashes are the main perturbations that can trigger performance-degrading, and potentially disruption-generating, neoclassical tearing modes. This Letter demonstrates sawtooth pacing by real-ti ...

Real-time plasma electron density profile estimation and control are essential in the operation of future tokamaks. In particular, the robustness against diagnostics failure and disturbances is important for long pulse operation. ...

Plasma initiation is an important phase in a tokamak discharge and its design and optimization is getting more and more attention in view of the operation of large tokamaks like ITER. The main objective of magnetic control during this phase is to obtain a ...

Federico Alberto Alfredo Felici

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Scenario optimization for the tokamak ramp-down phase in RAPTOR. Part B: safe termination of DEMO plasmas

Strategy to systematically design and deploy the ITER plasma control system: A system engineering and model-based design approach

Progress on the ITER Electron Cyclotron Heating and Current Drive Upper Launcher Steering Mirror Control System

Integrated Real-Time Supervisory Management for Off-Normal-Event Handling and Feedback Control of Tokamak Plasmas

Automated shot-to-shot optimization of the plasma start-up scenario in the TCV tokamak

Milestone in predicting core plasma turbulence: successful multi-channel validation of the gyrokinetic code GENE

Real-time feedback control of millimeter-wave polarization for LHD

Feedback control of ECRH polarization on LHD

Sawtooth pacing by real-time auxiliary power control in a tokamak

Model-based real-time plasma electron density profile estimation and control on ASDEX Upgrade and TCV

Iterative Learning Optimisation and Control of MAST-U Breakdown and Early Ramp-up Scenarios

Physics research on the TCV tokamak facility: from conventional to alternative scenarios and beyond

Control of NTMs and integrated multi-actuator control on TCV

Co- and Counter - viewing oblique ECE measurements during ECH and ECCD on the TCV tokamak