G. Manduchi
A5019980420- Magnetic confinement fusion research
- Particle accelerators and beam dynamics
- Superconducting Materials and Applications
- Advanced Data Storage Technologies
- Plasma Diagnostics and Applications
- Distributed and Parallel Computing Systems
- Ionosphere and magnetosphere dynamics
- Parallel Computing and Optimization Techniques
- Real-Time Systems Scheduling
- Fusion materials and technologies
- Particle Accelerators and Free-Electron Lasers
- Distributed systems and fault tolerance
- Embedded Systems Design Techniques
- Network Time Synchronization Technologies
- Scientific Computing and Data Management
- Laser-Plasma Interactions and Diagnostics
- Nuclear Physics and Applications
- Embedded Systems and FPGA Design
- Petri Nets in System Modeling
- Magnetic Field Sensors Techniques
- Advancements in PLL and VCO Technologies
- Atomic and Subatomic Physics Research
- Software Reliability and Analysis Research
- Plasma and Flow Control in Aerodynamics
- Sensor Technology and Measurement Systems
National Agency for New Technologies, Energy and Sustainable Economic Development
2015-2024
University of Padua
2015-2024
Institute for the Science and Technology of Plasmas
2023-2024
National Research Council
2017-2023
Innova (Italy)
2021
Institute of Ionized Gas
1995-2017
Institute of Electronics, Computer and Telecommunication Engineering
2017
University of Milan
2013
National Academies of Sciences, Engineering, and Medicine
2012
Istituto Nazionale di Fisica Nucleare, Sezione di Padova
1993
The ITER Neutral Beam Test Facility (NBTF), called PRIMA (Padova Research on Megavolt Accelerator), is hosted in Padova, Italy and includes two experiments: MITICA, the full-scale prototype of heating neutral beam injector, SPIDER, full-size radio frequency negative-ions source. NBTF realization exploitation SPIDER MITICA have been recognized as necessary to make future operation injectors efficient reliable, fundamental achievement thermonuclear-relevant plasma parameters ITER. This paper...
The ITER project requires additional heating by two neutral beam injectors, each accelerating to 1 MV a 40 A of negative deuterium ions, deliver the plasma power about 17 MW for one hour. As these requirements have never been experimentally met, it was recognized as necessary setup test facility, PRIMA (Padova Research on Megavolt Accelerator), in Italy, including full-size ion source, SPIDER, and prototype whole injector, MITICA, aiming develop injectors be installed ITER. This realization...
Abstract The negative-ion based neutral beam injector for heating and current drive of the ITER plasma (ITER HNB) is under development, at present focusing on optimization full-scale source in SPIDER test stand. production H − or D ions ion low work function surfaces obtained by caesium evaporation. This paper describes conditioning procedure corresponding performances during first operation with caesium. Technical solutions to overcome limitations stand are described. influence parameters...
We report on a set of performance measurements executed VMEbus MVME5500 boards equipped with MPC7455 PowerPC processor, running four different operating systems: Wind River VxWorks, Linux, RTAI, and Xenomai. Some components RTAI Xenomai have been ported to the target architecture. Interrupt latency, rescheduling inter-process communication times are compared in framework sample real-time application. Performance Gigabit Ethernet network also carried out boards. To this purpose, we considered...
Heating neutral beam (HNB) injectors, necessary to achieve burning conditions and control plasma instabilities in ITER, are characterized by such demanding parameters that a test facility (NBTF) dedicated their development optimization is being realized Padua (Italy) with direct contributions from the Italian government (through Consorzio RFX as host entity) ITER international organization (with kind domestic agencies of Europe, Japan India) technical scientific support various European...
The requirements of ITER neutral beam injectors (1 MeV, 40 A negative deuterium ion current for 1 h) have never been simultaneously attained; therefore, a dedicated Neutral Beam Test Facility (NBTF) was set up at Consorzio RFX (Padova, Italy). NBTF includes two experiments: SPIDER (Source the Production Ions Deuterium Extracted from Rf plasma), full-scale prototype source injectors, with 100 keV accelerator, to investigate and optimize properties source; MITICA, entire injector, devoted...
Abstract In magnetic fusion devices, error field (EF) sources, spurious perturbations, need to be identified and corrected for safe stable (disruption-free) tokamak operation. Within Work Package Tokamak Exploitation RT04, a series of studies have been carried out test the portability novel non-disruptive method, designed tested in DIII-D (Paz-Soldan et al 2022 Nucl. Fusion 62 126007), perform an assessment model-based EF control strategies towards their applicability ITER. this paper,...
MDSplus, a tree based, distributed data acquisition system, was developed in collaboration with the ZTH Group at Los Alamos National Lab and RFX CNR Padua, Italy. It is currently use MIT, TCV EPFL Lausanne, KBSI South Korea. MDSplus made up of set X/motif based tools for display, as well diagnostic configuration management. on hierarchical experiment description which completely describes analysis tasks contains results from these operations. These were designed to operate distributed,...
Stable operation with control on magnetohydrodynamic modes has been obtained in the modified reversed field experiment employing a set of 192 feedback controlled saddle coils. Improvements plasma temperature, confinement (twofold), and pulse length (threefold) and, as consequence magnetic fluctuation reduction, strong mitigation plasma-wall interaction mode locking are reported.Received 27 January 2006DOI:https://doi.org/10.1103/PhysRevLett.97.075001©2006 American Physical Society
Due to their discrete nature, a grid of active coils for the feedback control plasma instabilities produces an infinite sequence sideband harmonics in magnetic field. If sensors have same periodicity as coils, intelligent shell scheme (Bishop 1989 Plasma Phys. Control. Fusion 31 1179), aliasing sidebands determines systematic error on Fourier analysis measurements. Since relies raw measurements, it does not recognize effect. This is drawback field compensation and those perturbations that...
SPIDER is one of the two projects ITER Neutral Beam Test Facility (NBTF) under construction in Padova, Italy, at Consorzio RFX premises; it will have a 100 keV beam source with full-size prototype radiofrequency (RF) ion for Injector (NBI), designed to operate pulse length up 3600 s, featuring ITER-like filter field configuration, caesium oven layout and wide set diagnostics.These features allow reproducing operation like as cannot be done any other existing test facility.SPIDER realization...
RFX-mod is a Reversed Field Pinch device that allowed performing experiments in regimes with plasma current up to 2 MA, thanks its MHD active control system. Experiments have shown improved performances are obtained when the resonant part of m = 1 spectrum one dominant tearing mode much higher than other secondary ones (quasi single helicity states). Tearing modes play crucial role determining energy and particle transport. Based on present understanding interplay between passive conductive...
An overview of the recent operations and main results cesium injection in Source for Production Ions Deuterium Extracted from Rf plasma (SPIDER) negative ion source are described this contribution. In experiments without injection, all SPIDER plants were tested to verify basic expectations on operational parameters (e.g., electron cooling effectiveness magnetic filter field) determine its region. For beam properties, it was shown that current density varies across vertical direction....
Active feedback stabilization of multiple independent resistive wall modes is experimentally demonstrated in a reversed-field pinch plasma. A reproducible simultaneous suppression several nonresonant achieved. Coupling different due to the limited number coils observed agreement with theory. The RWMs also has an effect on tearing that are resonant central plasma, leading significant prolongation discharge pulse.
RFX-mod is a reversed field pinch (RFP) experiment equipped with system that actively controls the magnetic boundary. In this paper we describe results of new control algorithm, clean mode (CMC), in which aliasing sideband harmonics generated by discrete saddle coils corrected real time. CMC operation leads to smoother (i.e. more axisymmetric) Tearing modes rotate (up 100 Hz) and partially unlock. Plasma–wall interaction diminishes due decrease non-axisymmetric shift plasma column. With...
With the exploration of MA plasma current regime in up to 0.5 s long discharges, RFX-mod has opened new and very promising perspectives for reversed field pinch (RFP) magnetic configuration, made significant progress understanding improving confinement controlling stability. A big leap with respect previous knowledge expectations on RFP physics performance been by since last 2006 IAEA Fusion Energy Conference. self-organized helical equilibrium experimentally achieved (the Single Helical...
Active feedback control of resistive wall modes (RWMs) has been demonstrated in the EXTRAP T2R reversed-field pinch experiment. The system includes a sensor consisting an array magnetic coils (measuring mode harmonics) and actuator saddle coil (producing harmonics). Closed-loop (feedback) experiments using digital controller based on real time Fourier transform data have studied for cases where gain was constant all harmonics (corresponding to intelligent-shell) could be set selected...
We report on a set of performance measurements executed VMEbus MVME5500 boards equipped with MPC7455 PowerPC processor, running four different operating systems: Wind River VxWorks, Linux, RTAI, and Xenomai. Some components RTAI Xenomai have been ported to the target architecture. Interrupt latency, rescheduling inter-process communication times are compared in framework sample real-time application. Performance Gigabit Ethernet network also carried out boards. To this purpose, we considered...
Optimization of machine operation, including plasma position control, density control and especially feedback on multiple magnetohydrodynamic modes, has led RFX-mod to operate reliably at 1.5 MA, the highest current ever achieved a reversed field pinch (RFP). At high low magnetic topology spontaneously self-organizes in an Ohmical helical symmetry, with new axis helically twisting around geometrical torus. The separatrix island disappears leaving wide symmetric thermal structure large...