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Autor:
Neil Mitchell, Juan Knaster, Denis Bessette, E. Zapretilina, R. Gallix, A. Devred, L. Scibile, F. Rodriguez-Mateos
Publikováno v:
Fusion Science and Technology. 56:685-689
The Toroidal Field (TF) system of ITER consists of 18 coils with design nominal current of 68 kA operating in steady state mode that provides 5.4 T in the plasma centre. The winding pack (WP) of each coil is formed by 7 stacked double pancakes which
Autor:
V.E. Korsunsky, E. Zapretilina, S. Egorov, A. Bursikov, S.K. Samoylov, Igor Rodin, A. Lancetov
Publikováno v:
IEEE Transactions on Applied Superconductivity. 17:1489-1492
The toroidal field conductor insert (TFCI), a single layer coil wound from the Nb3Sn CICC intended for the ITER toroidal field coil, was tested in October 2001 at the JAERI test facility (Naka, Japan) as part of the ITER CSMC & Insert Test Program. D
Publikováno v:
IEEE Transactions on Applied Superconductivity. 16:803-806
A single layer solenoid, the Toroidal Field Conductor Insert (TFCI) was tested in October 2001 at JAERI test facility (Naka, Japan) as a part of the ITER CSMC & Insert Test Program. During the test campaign, the TFCI reached designed operating curren
Publikováno v:
IEEE Transactions on Applied Superconductivity. 16:795-798
Time-dependent thermal-hydraulic analyses of the ITER Toroidal Field (TF) Coils have been performed with a quasi-3D model based on the VINCENTA code. Two primary cooling loops are considered for the case and the winding pack respectively, each of the
Publikováno v:
IEEE Transactions on Applied Superconductivity. 16:827-830
AC loss curves measured for the same conductors at SULTAN (CRPP) and at University of Twente (UT) in higher and respectively lower frequency range are compared to draw consistent results. From the unified curves, the coupling time constant (n tau) to
Publikováno v:
IEEE Transactions on Appiled Superconductivity. 13:1424-1428
During 2000, AC losses and the effects of possible ramp-rate limitation (RRL) were investigated on the International Thermonuclear Experimental Reactor (ITER) Central Solenoid Insert Coil (CSIC), at JAERI Naka, Japan. The CSIC was mounted inside the
Autor:
Koji Yoshida, K Kitamura, Marco Ferrari, C. Jong, Kiyoshi Okuno, E. Zapretilina, Denis Bessette, M. Huguet, H. Takigami, N. Mitchell, Yuri Krivchenkov
Publikováno v:
Fusion Engineering and Design. :153-157
The design of the ITER magnet system is being finalized. The reference design of the winding pack of the TF coil is based on the use of circular conductors supported by radial plates. This design has been chosen for its high insulation reliability du
Publikováno v:
IEEE Transactions on Appiled Superconductivity. 11:1550-1553
Nb/sub 3/Sn and NbTi cable in conduit conductors (CICCs) cooled by a supercritical helium forced flow are considered in the ITER magnets. The design of the various CICCs relies on consideration of cost and manufacture as well as on the R&D performed
Publikováno v:
IEEE Transactions on Appiled Superconductivity. 10:1070-1073
The Central Solenoid Model Coil (CSMC) of the International Thermonuclear Experimental Reactor (ITER) will be installed and tested in 1999-2000 in a test facility at the Japan Atomic Energy Research Institute (JAERI) in Japan. The expected cable perf