Claudio Finotti
A5088799248- Magnetic confinement fusion research
- Superconducting Materials and Applications
- Particle accelerators and beam dynamics
- Fusion materials and technologies
- HVDC Systems and Fault Protection
- Plasma Diagnostics and Applications
- Particle Accelerators and Free-Electron Lasers
- Ionosphere and magnetosphere dynamics
- Silicon Carbide Semiconductor Technologies
- Nuclear reactor physics and engineering
- Power System Optimization and Stability
- Multilevel Inverters and Converters
- Laser-Plasma Interactions and Diagnostics
- Magnetic Field Sensors Techniques
- Microgrid Control and Optimization
- Atomic and Subatomic Physics Research
- Gyrotron and Vacuum Electronics Research
- Engineering Applied Research
- Advanced Adaptive Filtering Techniques
- Electric Motor Design and Analysis
- Advanced DC-DC Converters
- Pulsed Power Technology Applications
- Space Satellite Systems and Control
- Radio Frequency Integrated Circuit Design
- Analog and Mixed-Signal Circuit Design
National Agency for New Technologies, Energy and Sustainable Economic Development
2011-2022
University of Padua
2011-2022
University of Bologna
1997
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...
This paper reports the main recent results of RFX-mod fusion science activity.The device is characterized by a unique flexibility in terms accessible magnetic configurations.Axisymmetric and helically shaped Reversed-field pinch equilibria have been studied, along with tokamak plasmas wide range q(a) regimes (spanning from 4 down to 1.2 values).The full configurations between two, so-called ultra low-q ones, has explored, aim studying specific physical issues common all equilibria, such as,...
The RFX-mod device is operated both as a reversed field pinch (RFP), where advanced regimes featuring helical shape develop, and tokamak. Due to its flexibility, contributing the solution of key issues in roadmap ITER DEMO, including MHD instability control, internal transport barriers, edge turbulence, isotopic effect, high density limit three-dimensional (3D) non-linear modelling. This paper reports recent advancements understanding self-organized states, strong electron barrier, RFP...
This paper reports the highlights of RFX-mod fusion science programme since last 2010 IAEA Fusion Energy Conference. The focused on two main goals: exploring potential reversed field pinch (RFP) magnetic configuration and contributing to solution key technology problems in roadmap ITER. Active control several plasma parameters has been a tool this endeavour. New upgrades system for active magnetohydrodynamic (MHD) stability are underway will be presented paper. Unique among existing devices,...
The RFX-mod experiment is a fusion device designed to operate as reversed field pinch (RFP), with major radius m and minor m. Its high versatility recently allowed operating it also an ohmic tokamak, allowing comparative studies between the two configurations in same device. equipped state of art MHD mode feedback control system providing magnetic boundary effective control, by applying resonant or non-resonant perturbations (MP), both RFP tokamak configurations. In community application MPs...
A method to estimate the plasma boundary and global parameters such as βp+li/2 edge safety factor q95 is described. The based on poloidal flux extrapolation in vacuum region between magnetic measurements, it efficient accurate even if a limited set of sensors used. discrepancy provided by this computed Grad-Shafranov solver MAXFEA lower than 8 mm all considered cases. Moreover, robust against noise level present RFX-mod measurements. difference estimated simulation results 4%. was finally...
We present experimental results of magnetic feedback control on the m = 2, n 1 tearing mode in RFX-mod operated as a circular ohmically heated tokamak. The suppression non-resonant resistive wall (RWM) q(a) < 2 plasmas is well-established result RFX-mod. counterpart, which develops > equilibrium, instead more difficult issue. In fact, disruption induced by growing amplitude can be prevented only when resonant surface q close to plasma edge, namely 2.5, and electron density does not exceed...
In order to explore strategies reduce the high reactive power demand and improve current harmonic content injected into main grid of ITER experimental reactor, in this paper a different design approach ac/dc conversion system Acceleration Grid Power Supply (AGPS) Neutral Beam Injector based on Active Front End (AFE) solution is investigated. Particular attention has been given chosen modulation strategy, from that normally used AFE converter for application. Finally, performance AGPS...
The RAPTOR – RApid Plasma Transport simulatOR code is a model-based control-oriented that predicts Tokamak plasma profile evolution in real-time. One of its key applications state observer, where the real-time predictions are combined with measurements available diagnostics, yielding complete estimate profiles. observer currently installed control system TCV, it has been originally developed, ASDEX-Upgrade and recently RFX-mod. latter pioneered integration MARTe Multi-threaded Application...
The ITER pulsed power electrical network (PPEN) supplies the superconducting magnets and heating current drive systems. During experimental pulses, about several hundreds of seconds long, active consumption 500 MW reactive one 950 Mvar are expected. supply system is very large complex, a careful design required to assure safe operation. Stability PPEN has been already investigated in recent studies by numerical simulation analytical methods. Now, new dynamic model being developed, based on...
The ITER experiment is an international project that aims to prove the viability of energy production by a nuclear fusion reactor. reactions are achieved heating plasma up million Celsius degree and confining it means appropriate magnetic fields, which interact with charged particles plasma. In fields will be produced currents flowing in superconducting coils supplied ac/dc converters based on thyristor technology. power supply system may consume total active reactive respectively 500 MW 950...
The acceleration grid power supply (AGPS) of Megavolt ITER Injector and Concept Advancement (MITICA) test facility for the Neutral Beam (NBI) is a special system with demanding requirements (voltage -1 MV dc about 55 MW). procurement AGPS has been divided in two parts: medium-voltage switching conversion part high-voltage part. splitting required separation acceptance tests each individual scope supply, i.e., one had to be tested accepted without using other one. In this article, we deal...
The Reverse Field eXperiment (RFX) explores the physics of Pinch (RFP) plasmas as an alternative confinement option with respect to Tokamak and Stellarator concepts. toroidal field power supply RFX, modified upgraded during a long shut-down in 1999, is based on IGCTs (Integrated Gate Commutated Thyristors) combines extremely complex circuit topology fast, reliable flexible control system. It includes, among other devices, 12 dc/ac converters rated for 3kV, 6kA, pulse duty operation...