Title :
Results of the model coil tests for the cable-in-conduit conductor for SST-1 tokamak
Author :
Anashkin, O.P. ; Ivanov, D.P. ; Keilin, V.E. ; Kopeikin, N. Ph ; Kovalev, I.A. ; Krivykh, A.V. ; Kruglov, S.L. ; Lysenko, V.V. ; Novikov, S.I. ; Patrikeev, V.M. ; Pradhan, S. ; Saxena, Y.C. ; Scherbakov, V.I. ; Shugaev, I.O. ; Stepanov, V.V.
Author_Institution :
Kurchatov Inst., Moscow, Russia
fDate :
3/1/2002 12:00:00 AM
Abstract :
SST-1 tokamak, under fabrication at Institute for Plasma Research (IPR), India, deploys superconducting coils for both toroidal field (TF) and poloidal field (PF) magnets. A NbTi based 135 strands cable-in-conduit conductor (CICC) has been fabricated for this purpose by M/S Hitachi Cable Ltd. (Japan) under specification and supervision of IPR. In order to test the performance of this CICC under SST-1 operating scenarios, a Model Coil (MC) has been designed, fabricated and tested at Kurchatov Institute (KI), Russia using the SST-1 CICC under a collaborative program between IPR and KI. The MC was designed to have the same maximum field-to-current ratio (5 T at 10 kA) as of the SST-1 TF coils. Typical SST-1 disturbances were simulated with a toroidal array of four longitudinal disturbances simulating coils and with two transverse disturbances simulating coils.
Keywords :
Tokamak devices; fusion reactor design; superconducting coils; superconducting magnets; 10 kA; 5 T; SST-1 tokamak; cable-in-conduit conductor; fusion reactors; model coil tests; poloidal field magnets; superconducting coils; toroidal field magnets; transverse disturbances; Conductors; Fabrication; Intellectual property; Magnets; Niobium compounds; Plasmas; Superconducting cables; Superconducting coils; Testing; Tokamaks;
Journal_Title :
Applied Superconductivity, IEEE Transactions on
DOI :
10.1109/TASC.2002.1018467
