Boris Stepanov

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The performance degradation under electro-magnetic, transverse load has grown to a key issue for the design of Nb<sub>3</sub>Sn cable-in-conduit conductors (CICC). Beside the tolerance to bending strain of the basic Nb<sub>3</sub>Sn strand and the void fraction of the CICC, a relevant parameter is thought to be the cable pattern. A sequence of(More)
In the scope of the qualification tests of the ITER TF conductors, four samples for the SULTAN facility have been prepared, each consisting of two conductor sections manufactured by the US ITER Domestic Agency. The samples are nicknamed USTF1, USTF2, USTF3 and USTF4. The conductor sections used for USTF1 and USTF3, as well as those for USTF2 and USTF4, are(More)
Japan Atomic Energy Agency (JAEA) has fabricated and tested the four conductor samples composed of high performance strands manufactured by the bronze-route process for the ITER Central Solenoid (CS) conductor. The current sharing temperature (Tcs) electrically assessed at 45.1 K and 10.85 T along the cycling loading at 48.8 kA and 10.85 T initially were(More)
Performance verification of the Nb<sub>3</sub>Sn cable-in-conduit conductor (CICC) for the series-connected hybrid magnets at the National High Magnetic Field Laboratory (NHMFL) and Helmholtz Centre Berlin is performed through short sample testing. The superconducting outsert coil consists of three CICC configurations, graded for the applied magnetic field.(More)
The ITER central solenoid (CS) must be capable of driving inductively 30 000 15 MA plasma pulses with a burn duration of 400 s. This implies that during the lifetime of the machine, the CS, comprised of six independently powered coil modules, will have to sustain severe and repeated electromagnetic cycles to high current and field conditions. The design of(More)
Many full size conductors for the ITER TF coils have been tested at the SULTAN test facility in Switzerland for conductor qualification. JAEA tested two samples and two kinds of Nb<sub>3</sub>Sn strands were evaluated through the tests. Now another sample named JATF3 has been tested, which uses two other kinds of Nb<sub>3</sub>Sn strands. The strands(More)
The DEMO plant will demonstrate by mid-century the feasibility of electric power generation by nuclear fusion. In the scope of design studies coordinated by the European Commission, CRPP and ENEA are developing two force flow conductor layouts as candidates for the toroidal field (TF) coils of DEMO. The operating conditions include 82 kA operating current(More)
In the framework of the JT-60SA project, included inside the Broader Approach agreement, EU is expected to provide to JA the totality of the toroidal field (TF) magnet system. It consists in 18 coils, evenly shared for in-kind procurement between France and Italy while the TF conductor providing is under the responsibility of Fusion for Energy. The(More)
Superconductors for the ITER Poloidal Field Coils are large cable-in-conduit conductors (CICC) made of NbTi strands encased in a round-in-square stainless steel jacket. Three prototype conductor sections for poloidal field coils PF1/6, PF2/3/4 and PF5 have been fabricated in collaboration of the domestic RF, CN and EU agencies and tested in SULTAN Test(More)
Two short length samples have been prepared and tested in SULTAN to benchmark the performance of high current density, advanced Nb<sub>3</sub>Sn strands in the large cable-in-conduit conductors (CICC) for ITER. The cable pattern and jacket layout were identical to the toroidal field model coil conductor (TFMC), tested in 1999. The four conductor sections(More)