- Particle accelerators and beam dynamics
- Superconducting Materials and Applications
- Magnetic confinement fusion research
- Fusion materials and technologies
- Spacecraft and Cryogenic Technologies
- Plasma Diagnostics and Applications
- Quantum, superfluid, helium dynamics
- Advanced Thermodynamic Systems and Engines
- Superconductivity in MgB2 and Alloys
- Atomic and Subatomic Physics Research
- Advanced Condensed Matter Physics
University of Padua
2021
National Agency for New Technologies, Energy and Sustainable Economic Development
2021
Fusion for Energy
2012-2020
Oxford Instruments (United Kingdom)
2010-2012
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...
Cryogenic equipment can be found in the majority of neutron scattering experiments. Recent increases liquid helium cost caused by global supply problems lead to significant concern about affordability conventional cryogenic equipment. However latest progress cryo-cooler technology offers a new generation systems which cryogen consumption significantly reduced and some cases completely eliminated. These also offer advantage operational simplicity, require less space than cryogen-cooled...
Recent advances in superconducting technology and cryocooler refrigeration have resulted a new generation of advanced magnets for neutron beam applications. These outstanding parameters such as high homogeneity stability at highest magnetic fields possible, reasonably small stray field, low scattering background larger exposure to detectors. At the same time pulse tube provides complete re-condensing regime which allows minimise requirements cryogens without introducing additional noise...
The thermal shields of the ITER machine must be cooled using helium circulating at 80 K. cryopumps also require intermittent cooling power this temperature level. As a result two forcedflow loops supplied by liquid nitrogen have been developed. Each K loop comprises an integrally geared centrifugal compressor able to compress up 4 kg/s between 1.6 and 1.8 MPa perlite insulated cold box. This paper outlines process requirements for design chosen in order answer them. It justifies technology...
The ITER Tokamak Magnets, Thermal Shields and Cryopumps require a considerable cryogenic power. To supply an average power of 75 kW eq.@4.5 K 600 kW@80K, several helium refrigerators are used, relying on LN2 for cooling or pre-cooling: this cold is ensured by 2x refrigerators. Due to the time dependent heat load clients, capacity generated LN2Plants has vary from 870 1200 eq.@80K resulting in alternating liquefaction refrigeration modes. This type unit, seldom used scientific facilities,...
The toroidal field magnets of ITER contain over 7 tons helium. Most the inventory is expelled from in case a quench and it needs to be captured external storage vessels (Quench Tanks). Force cooled technology with gas circulation was chosen for these order optimize their footprint, risks, costs. This paper outlines input data, assumptions, studies performed choose most appropriate Quench Tanks. Further demonstrate feasibility ensure required performance, as well some peculiarities design...
The Warm Regeneration Lines are a system of about 500 meters flexible cryogenic transfer lines for the System ITER fusion reactor. have been designed to helium gas in temperature range 100K/500K and pressure 1.2MPa/1.8MPa, regeneration cryopumps Torus Vacuum Vessel, Cryostat Neutral Beam injector's vessel cool-down/warmup from/to room temperature.
Thermal shields of ITER machine and cryopumps are cooled by two forced-flow helium cooling loops using at 80 K as a media liquid nitrogen source cooling. Two-stage integrally geared centrifugal compressors provide mass flow up to 4 kg/s per each with suction discharge pressure 1.6 1.8 MPa correspondingly. This is the first in world use such machines for helium, therefore an extensive testing program was developed demonstrate much possible that required performance achieved. paper presents...