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

Volume

12

Issue

1

fYear

2002

fDate

3/1/2002 12:00:00 AM

Firstpage

567

Lastpage

570

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;

fLanguage

English

Journal_Title

Applied Superconductivity, IEEE Transactions on

Publisher

ieee

ISSN

1051-8223

Type

jour

DOI

10.1109/TASC.2002.1018467

Filename

1018467