A5040925469- Superconducting Materials and Applications
- Particle accelerators and beam dynamics
- Magnetic confinement fusion research
- Physics of Superconductivity and Magnetism
- Fusion materials and technologies
- HVDC Systems and Fault Protection
- Superconductivity in MgB2 and Alloys
- Spacecraft and Cryogenic Technologies
- Magnetic properties of thin films
- Thermal Analysis in Power Transmission
- Advanced Condensed Matter Physics
- ZnO doping and properties
- Electromagnetic Launch and Propulsion Technology
- Magnetic and transport properties of perovskites and related materials
- High-pressure geophysics and materials
- Nuclear Physics and Applications
- Non-Destructive Testing Techniques
- Copper Interconnects and Reliability
- Particle Accelerators and Free-Electron Lasers
- Electromagnetic Simulation and Numerical Methods
- Electromagnetic Compatibility and Noise Suppression
- Electronic Packaging and Soldering Technologies
- Electronic and Structural Properties of Oxides
- Geophysical Methods and Applications
- Nuclear and radioactivity studies
ITER
2013-2024
Fusion for Energy
2008-2010
Kerntechnische Entsorgung Karlsruhe (Germany)
2008
General Electric (Austria)
2001-2006
FZI Research Center for Information Technology
2005
Max Planck Computing and Data Facility
2005
Max Planck Institute for Plasma Physics
2003
Universities Austria
1998-2003
University of Vienna
1997
Taking the relay of large Hadron collider (LHC) at CERN, ITER has become largest project in applied superconductivity. In addition to its technical complexity, is also a management challenge as it relies on an unprecedented collaboration seven partners, representing more than half world population, who provide 90% components in-kind contributions. The magnet system one most sophisticated superconducting systems ever designed, with enormous stored energy 51 GJ. It involves six partners. coils...
The ITER magnet coils are wound from Cable-In-Conduit Conductors (CICC) made up of superconducting and copper strands assembled into a multistage, rope-type cable inserted conduit butt-welded austenitic steel tubes. conductors for the Toroidal Field (TF) Central Solenoid (CS) require about 500 tons Nb <sub xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">3</sub> Sn while Poloidal (PF) Correction Coil (CC) need around 250 Nb-Ti strands. required amount...
The differences in thermal contraction of the composite materials a cable conduit conductor (CICC) for International Thermonuclear Experimental Reactor (ITER), combination with electromagnetic charging, cause axial, transverse contact and bending strains Nb3Sn filaments. These local loads distributed strain alterations, reducing superconducting transport properties. sensitivity ITER strands to different is experimentally explored dedicated probes. starting point characterization measurement...
The performance of the toroidal field (TF) magnet conductors for ITER machine are qualified by a short full-size sample (4 m) current sharing temperature (T-cs) test in SULTAN facility at CRPP Villigen, Switzerland, using operating 68 kA and design peak 11.8 T. Several samples, including least one from each six Domestic Agencies participating TF conductor fabrication (China, European Union, Japan, Russia, South Korea United States), have been Organization after achieving T-cs values 6.0-6.9...
The ITER central solenoid (CS) must be capable of driving inductively 30 000 15 MA plasma pulses with a burn duration 400 s. This implies that during the lifetime machine, CS, comprised six independently powered coil modules, will have to sustain severe and repeated electromagnetic cycles high current field conditions. design CS calls for use cable-in-conduit conductors made up pure copper strands, assembled in five-stage, rope-type cable around cooling spiral is inserted into...
In the frame of European Fusion Technology Programme, Forschungszentrum Karlsruhe and CRPP Villigen have designed built a 70 kA current lead for ITER TF Coils using High Temperature Superconductors (HTS). At beginning 2004 HTS was installed tested in TOSKA facility Karlsruhe. The scope experiment to characterize steady state conditions explore operation limits as well. For this, temperature profile, contact resistances, heat load at 4.5 K, required 50 K He mass flow rate, margin were...
A new generation of ITER TF conductor samples has been assembled and tested in SULTAN 2007 following a common procedure agreed among the parties. The test results six samples, made twelve sections manufactured Europe, Japan, Korea Russia, are reported here. layout reflects design, with minor differences for Nb <sub xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">3</sub> Sn strand characteristics, void fraction twist pitch. object is straight...
<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...
We analyzed the ITER TFEU5 cable-in-conduit conductor (CICC) after full SULTAN qualification test in order to explore whether Lorentz force induced strand movement inside CICC produces any fracture of brittle Nb3Sn filaments. Metallographic image analysis was used quantify change void fraction each sub-cable (petal); strands move direction force, increasing space on low side and producing a densification high side. Adjacent counting shows that local increases result lower strand–strand...
Two short length samples have been prepared and tested in SULTAN to benchmark the performance of high current density, advanced Nb <sub xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink">3</sub> Sn strands large cable-in-conduit conductors (CICC) for ITER. The cable pattern jacket layout were identical toroidal field model coil conductor (TFMC), 1999. four sections used from OST, EAS, OKSC OCSI respectively. Cu:non-Cu ratio was 1 three new strands,...
In this paper we report the main test results obtained on Poloidal Field Conductor Insert coil (PFI) for International Thermonuclear Experimental Reactor (ITER), built jointly by EU and RF ITER parties, recently installed tested in CS Model Coil facility, at JAEA-Naka. During (a) verified DC AC operating margin of NbTi Cable-in-Conduit conditions representative operation PF coils, (b) measured intermediate conductor joint resistance, loss, (c) loss its changes once subjected to a significant...
The performance degradation under electro-magnetic, transverse load has grown to a key issue for the design of 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). Beside tolerance bending strain basic strand and void fraction CICC, relevant parameter is thought be cable pattern. A sequence ldquolongrdquo twist pitches in early stages multi-stage credited mitigate compared ldquoshortrdquo pitches. To...
The latest achievements in the development of high performance Nb3Sn strands are reported. In field energy physics (HEP) critical current densities up to 3000 A mm−2 (at 12 T, 4.2 K and 10 µV m−1) can be achieved. Current actions aimed at reducing filament size about 50 µm decreasing production costs by using less expensive base materials. order take advantage progress made HEP R&D program, fusion community has initiated several strand procurement worldwide produce advanced types fulfilling...
<para xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink"> Following the outcome of conceptual design phase EFDA dipole magnet will be made rectangular Cable-in-Conduit Conductors (CICC) jacketed in 316LN. In order to optimize required amount superconductor two different conductor types are used: a high-field (HF) consisting 144 strands and low-field (LF) with 108 strands. A high <formula formulatype="inline"> <tex>${\rm J}_{\rm c}$</tex></formula>...
The ITER magnet system uses cable-in-conduit conductor (CICC) technology with individual strands twisted in several stages resulting a rope-type cable, which is inserted into stainless steel conduit. combination of high current (up to 68 kA) and background magnetic field 13 T) results large transverse Lorentz forces exerted on the conductors during operation. forces, accompanied cyclic nature load, have strong influence properties. Twente Cryogenic Cable Press used simulate effect comparable...
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...
<para xmlns:mml="http://www.w3.org/1998/Math/MathML" xmlns:xlink="http://www.w3.org/1999/xlink"> The world-wide procurement of <formula formulatype="inline"><tex Notation="TeX">${\rm Nb}_{3}{\rm Sn}$</tex></formula> and NbTi for the ITER superconducting magnet systems will involve eight to ten strand suppliers from six Domestic Agencies (DAs) on three continents. To ensure accurate consistent measurement physical properties composite strand, a test facility benchmarking effort was initiated...
In the frame of European Fusion Technology Programme, Forschungszentrum Karlsruhe and Centre de Recherches en Physique des Plasmas, CRPP, Villigen, develop a 70 kA current lead to demonstrate feasibility usage High Temperature Superconductors (HTS) for leads ITER TF coils. Design fabrication conventional heat exchanger that covers temperature range from 65 K room is done at Karlsruhe. The HTS module connects feeder terminal 4.5 with cooled only by conduction cold end. Its design has been...
One of the design features which yet offers interesting margins for performance optimization cable-in-conduit conductors (CICCs), is their geometry. For relatively small size Nb3Sn CICCs, operating at high electromagnetic pressure, such as those EDIPO project, it has been experimentally shown that a based on rectangular layout with higher aspect ratio leads to best performance, especially in terms degradation loads. To extend this analysis larger we manufactured and tested, SULTAN facility,...
NbTi strands to be used in four of the six ITER poloidal field (PF) coils, all correction coils (CC) and superconducting feeder busbars are being produced China. Short full-size qualification conductor (cabled jacketed) samples have been developed at ASIPP tested CRPP. Single pinning mechanism parametrization for this Chinese strand (type S2) has obtained using Bottura scaling law. The determination parameters a Kramer-type regression method will described. A comparison between critical...