A. Luchetta

ORCID: 0000-0002-5657-1270
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About
Contact & Profiles
Research Areas
  • Magnetic confinement fusion research
  • Particle accelerators and beam dynamics
  • Superconducting Materials and Applications
  • Plasma Diagnostics and Applications
  • Advanced Data Storage Technologies
  • Distributed and Parallel Computing Systems
  • Particle Accelerators and Free-Electron Lasers
  • Fusion materials and technologies
  • Real-Time Systems Scheduling
  • Network Time Synchronization Technologies
  • Distributed systems and fault tolerance
  • Embedded Systems and FPGA Design
  • Parallel Computing and Optimization Techniques
  • Ionosphere and magnetosphere dynamics
  • Embedded Systems Design Techniques
  • Advancements in PLL and VCO Technologies
  • Magnetic Field Sensors Techniques
  • Smart Grid Security and Resilience
  • Sensor Technology and Measurement Systems
  • Scientific Computing and Data Management
  • Gyrotron and Vacuum Electronics Research
  • Experimental Learning in Engineering
  • Advanced Frequency and Time Standards
  • Industrial Automation and Control Systems
  • Nuclear Physics and Applications

Institute for the Science and Technology of Plasmas
2021-2023

National Agency for New Technologies, Energy and Sustainable Economic Development
2013-2023

University of Padua
1995-2023

University of Milan
2013

Institute of Ionized Gas
1986-1996

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...

10.1088/1367-2630/aa78e8 article EN cc-by New Journal of Physics 2017-08-25

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...

10.1088/0029-5515/55/8/083025 article EN Nuclear Fusion 2015-07-21

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...

10.1088/1741-4326/ac715e article EN Nuclear Fusion 2022-05-23

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...

10.1109/tns.2007.905231 article EN IEEE Transactions on Nuclear Science 2008-01-01

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...

10.1088/1741-4326/ab2271 article EN Nuclear Fusion 2019-05-17

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...

10.1063/1.5133076 article EN Review of Scientific Instruments 2020-02-01

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...

10.1088/1741-4326/aa7490 article EN Nuclear Fusion 2017-05-22

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....

10.1109/tps.2022.3226239 article EN IEEE Transactions on Plasma Science 2023-01-20

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...

10.1109/rtc.2007.4382787 article EN 2007-04-01

The ITER project requires additional heating by two neutral beam injectors, each accelerating to 1MV a 40A of negative deuterons, delivering the plasma about 17MW up one hour. As these requirements have never been experimentally met, it was decided build 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. Japan India Domestic Agencies participate...

10.1063/1.4792827 article EN AIP conference proceedings 2013-01-01

MITICA is one of the two ongoing experiments at ITER neutral beam test facility (NBTF) located in Padua (Italy). aims to develop full-size injector and, as such, its Control and Data Acquisition System will adhere CODAC directives. In particular, timing system be based on IEEE1588 PTPv2 protocol it use time communication network (TCN) a dedicated Ethernet local-area network. Following device catalog, National Instruments PXI-6683H precision (PTP) modules used generate triggers clocks...

10.1109/tns.2023.3237003 article EN IEEE Transactions on Nuclear Science 2023-01-16

The EPICS Channel Archiver is used to store data ex ported by I/O Controllers. acts as a Access Client and stores recorded data, acquired via periodic scan or monitored, into indexed binary files. MDSplus management system in several Nuclear Fusion experiments handle experimental configuration data. A access Application Programming Interface for local remote available languages, namely C, C++, Fortran, Java, Python, MATLAB IDL, set of visualization tools browsing display. paper presents new...

10.1109/tns.2011.2167349 article EN IEEE Transactions on Nuclear Science 2011-10-13

The electrical insulation of the Megavolt ITER Injector and Concept Advancement (MITICA) beam source (BS) at 1 MV in vacuum is a challenging issue, which could not be fully addressed so far on basis experimental results theoretical models available literature. A specific high-voltage (HV) test campaign being prepared to validate optimize voltage holding capability BS under realistic conditions, using full-size mockup electrodes reproducing detail geometry accelerator. proposed strategy will...

10.1109/tps.2022.3168341 article EN IEEE Transactions on Plasma Science 2022-04-29

10.1016/j.fusengdes.2004.04.007 article EN Fusion Engineering and Design 2004-06-01
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