ITER toroidal field model coil (TFMC)

E. Salpietro, R. Maix, G. Bevilacqua, G. Di Bartolo, H. Fillunger, N. Mitchell, B. Turck, P. Libeyre, A. Ulbricht, M. Spadoni, A. Della Corte, H. Bieder, D. Bresson, D. Krischel, G.E. Tardivelli

Research output: Contribution to journalArticle

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Abstract

The TF coils for ITER will use the concept of a circular thin walled Nb3Sn cable in conduit superconductor completely in an insulated groove in steel plates to form the coil pancakes. This concept is being demonstrated by the fabrication of a TFMC (Toroidal Field Model Coil) for ITER. The coil will be tested during 1999 in the TOSKA facility at FZK, Karlsruhe, using the EURATOM LCT coil to provide an external field system.
Original languageEnglish
Pages (from-to)151 - 158
Number of pages8
JournalFusion Engineering and Design
Volume46
Issue number2-4
DOIs
Publication statusPublished - 1999
Externally publishedYes

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All Science Journal Classification (ASJC) codes

  • Civil and Structural Engineering
  • Nuclear Energy and Engineering
  • Materials Science(all)
  • Mechanical Engineering

Cite this

Salpietro, E., Maix, R., Bevilacqua, G., Di Bartolo, G., Fillunger, H., Mitchell, N., Turck, B., Libeyre, P., Ulbricht, A., Spadoni, M., Della Corte, A., Bieder, H., Bresson, D., Krischel, D., & Tardivelli, G. E. (1999). ITER toroidal field model coil (TFMC). Fusion Engineering and Design, 46(2-4), 151 - 158. https://doi.org/10.1016/S0920-3796(99)00042-3