A5048656190- Superconducting Materials and Applications
- Particle accelerators and beam dynamics
- Magnetic confinement fusion research
- Gyrotron and Vacuum Electronics Research
- Fusion materials and technologies
- Physics of Superconductivity and Magnetism
- Nuclear reactor physics and engineering
- Geophysical Methods and Applications
- Thermal Analysis in Power Transmission
- Superconductivity in MgB2 and Alloys
- Non-Destructive Testing Techniques
- Magnetic Properties and Applications
- Ultrasonics and Acoustic Wave Propagation
- Microwave Engineering and Waveguides
- HVDC Systems and Fault Protection
- Spacecraft and Cryogenic Technologies
- Electromagnetic Scattering and Analysis
- Acoustic Wave Resonator Technologies
- Particle Accelerators and Free-Electron Lasers
- Electromagnetic Simulation and Numerical Methods
- Nuclear Engineering Thermal-Hydraulics
- Induction Heating and Inverter Technology
- Nuclear Physics and Applications
- Structural Health Monitoring Techniques
- Electromagnetic Compatibility and Measurements
Fusion for Energy
2015-2024
Polytechnic University of Turin
2017
École Polytechnique Fédérale de Lausanne
2008-2010
University of Cagliari
2005-2008
Kerntechnische Entsorgung Karlsruhe (Germany)
2008
<para xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink"> Four <formula formulatype="inline"><tex>${\rm Nb}_{3}{\rm Sn}$</tex> </formula> conductor lengths were prepared according to the ITER TF design and assembled into two SULTAN samples. The four are not fully identical, with variations of strand supplier, void fraction twist pitch. Lower fractions improve support increased pitches also lower contact pressure but both tend increase AC loss increases...
In the last decade, a large number of high current, force flow superconductors have been tested as short length samples in SULTAN facility. The object test ranged over transient stability, thermal-hydraulic behavior, AC losses, joint resistance and proof-of-principle for innovative conductor design. Recently, with ITER cable-in-conduit conductors (CICC), basic DC transport properties focus test. critical steps sample assembly instrumentation are described, emphasis on application temperature...
A 12.5 T superconducting dipole magnet (European DIPOle, EDIPO) has been designed by EFDA and it is now being procured within the framework of European Fusion Programme in order to be installed CRPP-PSI. This saddle-shaped reach a 100 times 150 mm rectangular bore over length about 1.5 m test full size conductor samples that shall produced during ITER magnets procurement. The uses Cable In Conduit Conductor (CICC) technology cables are made high Jc (about 2300 A/mm <sup...
One year of operation and test activity the SULTAN facility at CRPP-Villigen, from October 2008 to 2009 is reviewed. The main improvements include a new control system for cryo-plant electric motor helium compressor. range samples has been improved in terms cyclic loading rate. campaigns eight ITER TF conductor samples, two JT60SA number other developmental samples. highlights campaign statistical data about cool-downs, warm-ups duration are reported. For more detail given joint development,...
The upgrade to JT-60SA tokamak (R = 3m, a 1.2m) was conducted within Europe-Japan collaboration agreement featuring the implementation of superconducting magnets. In 2021, magnet system commissioning initiated, undergoing cool-down and energization 18 Nb-Ti Toroidal Field (TF) coils (400 tonnes) up full nominal current. TF smoothly processed but it observed during current load higher outlet temperature increase TF02 coil versus others, indicating resistance in this circuit therefore possible...
An iterative procedure is described, which models the influence of thermal expansion gyrotron cavity on expected performance. It a multiphysics simulation method, involves electrodynamic, thermal-hydraulic, and thermo-mechanical simulations. The method applied to first European 170-GHz, 1-MW continuous wave prototype for ITER. According simulations, performance reduction ~15% at nominal operating parameters, because cavity. Alternative points mitigate this effect are proposed numerically...
The EDIPO test facility is erected at CRPP Villigen with the aim of providing a flexible, high field bed for current force flow superconductors. main coil tilted-head race-track pair wound by graded Nb3Sn cable-in-conduit conductor. whole project, partly funded European Commission, started in 2004 and entered commissioning phase 2013. final steps instrumentation installation coil, delivered industry May 2011, lasted about 18 months. first cool-down November 2012. including precise...
Advances in the performance of low- and high-temperature superconductors enable development advanced magnets for a range applications, including tokamaks fusion energy, dipoles, quadrupoles hadron colliders, solenoids nuclear magnetic resonance studies. The capability testing prototype cables insert coils at high field is critical to these developments. We present here conceptual design test facility dipole with features suitable support magnet efforts both Fusion HEP communities. In...
Based on the functional specification by ITER organization, CRPP developed a design proposal for magnet feeder busbar system. The magnetic field level estimated operation of busbars allows use NbTi superconductor. minimum superconducting cross sections and copper stabilizers are calculated based temperature margin 2.5 K safe hot spot temperature. these cable layout has been identified each type optimization parameters performed with thermo-hydraulic codes. margins have established...
The change of length upon heat treatment steel jacketed, Nb <sub xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">3</sub> Sn cable-in-conduit conductors (CICC) is driven by the difference coefficient thermal expansion between and other components. cold work jacket also plays an important role. During preparation CICC samples for test in SULTAN facility, has been systematically measured 16 sections CICC. broad range changes, from elongation to...
Since it is practically impossible to remove the Poloidal Field (PF) coils from assembled ITER (International Thermonuclear Experimental Reactor) tokamak without major interruption in operation, design of these shall provide their high reliability under voltage operation. The coil insulation relies on a separation functions: mechanical function load transmission, performed by glass-fiber impregnated with epoxy resin one side, and independent electrical barrier made polyimide tapes other...
A large aperture Nb3Sn dipole is proposed to replace the magnet assembly of EDIPO, which was irreversibly damaged in 2016. The goal generate a background field 15 T at 4.2 K clear approximately 100×150 mm <sup xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">2</sup> and over uniform length 1000 order test superconducting cables for both fusion high-energy physics applications. features block-type coil design wound with wide Rutherford cable (two...
During the commissioning phase of JT-60SA magnet system, which included cool-down in 2020 and energization 18 Toroidal Field (TF) coils up to a nominal current 25.7 kA 2021, combined helium flow issued from TF02 coil feeder outlet showed higher temperature profile than one other TF when energized, pointing presence an extra joint resistance associated circuit. To analyze this excursion potential risks, hydraulic circuit have been modelled with thermo-hydraulic CryoSoft suite framework...
All the ITER superconductors are tested as short length samples in SULTAN test facility at CRPP. Twenty-four TF conductor with small layout variations were since February 2007 aim of verifying design and qualification manufacturers. The sample assembly measurement techniques CRPP discussed. Starting 2010, another for conductors, named EDIPO, will be operating to share load acceptance tests during construction ITER.
Three different pressurized subcooled water cooling options [hypervapotron, mini-channels (MCs), and meander flow drivers] for a full-size gyrotron cavity are developed analyzed using the commercial computational fluid dynamics code STAR-CCM+, to guarantee pressure drop below maximum acceptable, compliance with manufacturing constraints. The designs then transposed corresponding mock-ups identify most suitable candidate an experimental test. conjugate multiphase heat transfer problem is...
The coupling loss in a cable conduit conductor (CICC) is strongly influenced by the geometry. Beside pattern, twist pitch, wrapping and void fraction, also aspect ratio has not negligible role loss. In fact, it defines area crossed flux variation determines therefore entity of current between strands. An AC experiment on two Nb <sub xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">3</sub> Sn CICC samples (PITSAM II PITSAM III) carried out with...
In cabled conductors a perfect uniformity of the current among strands is hardly reached, due to non-homogeneity contact resistance distribution between and copper electrical terminations. case large unbalance, overloaded hit critical surface at high field early, developing sharing voltage, which drives redistribution current, mainly in terminations where inter-strand lower than conductor. If termination low, voltage levels are sufficiently low allow an effective less loaded strands.