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Development of a 20 kA high temperature superconductor current lead.

Author(s) : HELLER R., FRIESINGER G., FUCHS A. M., et al.

Type of article: Article

Summary

In the framework of the European Fusion Technology Programme, a development program has been carried out for design and construction of a 68 kA current lead for the toroidal field (TF) coils of the International Thermonuclear Experimental Reactor, ITER, using HTS. The material selection, based on test results of 1 kA current leads, favoured the use of Bi-2223 stabilized tapes because of the higher thermal stability. Two 10 kA HTS modules were manufactured in industry and tested in a test facility at covered the electrical and thermal behaviour in both steady-state and transient operation.

Details

  • Original title: Development of a 20 kA high temperature superconductor current lead.
  • Record ID : 2003-0581
  • Languages: English
  • Source: Cryogenics - vol. 41 - n. 8
  • Publication date: 2001/08

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