Title of article :
Design and manufacture of the Poloidal Field Conductor Insert coil
Author/Authors :
Sborchia، نويسنده , , C. and Duglue، نويسنده , , D. and Hurd، نويسنده , , F. and Maix، نويسنده , , R. and Salpietro، نويسنده , , E. and Testoni، نويسنده , , P. and Bessette، نويسنده , , D. and Mitchell، نويسنده , , N. and Okuno، نويسنده , , K. and Sugimoto، نويسنده , , M. and Alekseev، نويسنده , , A. and Sytnikov، نويسنده , , V.، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2003
Pages :
6
From page :
1081
To page :
1086
Abstract :
The Poloidal Field (PF) coils of ITER (International Thermonuclear Experimental Reactor) will supply the necessary magnetic field to initiate, shape, control and shutdown burning plasmas. The PF coils use NbTi cable-in-conduit superconductors, which operate at maximum currents of the order of 45–60 kA and experience large variations of current and magnetic fields. In order to test full-scale NbTi superconductors at operational conditions similar to ITER, the European Team has been asked to design and manufacture a PF conductor insert (PFCI). The cable has been provided by the Russian Federation. The Insert will be tested in 2004 in the Central Solenoid Model Coil (CSMC) facility at JAERI Naka, Japan.
Keywords :
ITER , Poloidal field coils , NbTi cable in-conduit
Journal title :
Fusion Engineering and Design
Serial Year :
2003
Journal title :
Fusion Engineering and Design
Record number :
2369473
Link To Document :
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