• DocumentCode
    55040
  • Title

    Preliminary Performance Test Results of First CICC From Korea Destined for an ITER TF Magnet

  • Author

    Soun Pil Kwon ; Soo-Hyeon Park ; Stepanov, Boris ; Bruzzone, Pierluigi ; Keeman Kim

  • Author_Institution
    ITER Korea, Nat. Fusion Res. Inst., Daejeon, South Korea
  • Volume
    23
  • Issue
    3
  • fYear
    2013
  • fDate
    Jun-13
  • Firstpage
    4201705
  • Lastpage
    4201705
  • Abstract
    The Republic of Korea is participating in the ITER project to construct and operate the ITER tokamak for the purpose of demonstrating the feasibility of fusion power. ITER Korea, the implementing agency for the Republic of Korea that is procuring items for the ITER project on behalf of the Korean government, has established domestic and international contracts for the procurement of cable-in-conduit conductor (CICC) that will be used in the ITER toroidal field (TF) magnets. The CICC for the ITER TF magnets is made of superconducting and copper strand cable inside a cylindrical stainless steel jacket, and is designed to operate at a nominal peak field of 11.8 T at 4.5 K with 68 kA of nominal operating current. Recently, the first CICC from Korea, which will be installed in an ITER TF magnet, has been manufactured and tested including testing performed on a 4 m sample near ITER operating conditions at the CRPP-EPFL SULTAN facility in Villigen, Switzerland under the coordination of the ITER International Organization. This paper provides a brief description of the CICC along with preliminary results of the tests and the conductor performance characteristics derived from the results.
  • Keywords
    Tokamak devices; niobium alloys; plasma toroidal confinement; superconducting cables; superconducting magnets; tin alloys; CICC; CRPP-EPFL SULTAN facility; ITER International Organization; ITER Korea; ITER TF magnets; ITER operating conditions; ITER project; ITER tokamak; ITER toroidal field magnets; Korean government; Nb3Sn; Switzerland; Villigen; cable-in-conduit conductor procurement; conductor performance; copper strand cable; current 68 kA; cylindrical stainless steel jacket; fusion power feasibility; magnetic flux density 11.8 T; nominal operating current; size 4 m; superconducting cable; temperature 4.5 K; Cable shielding; Conductors; Current measurement; Niobium-tin; Superconducting cables; Superconducting magnets; Temperature measurement; Cable-in-conduit; ITER; SULTAN; internal tin $ hbox{Nb}_{3}hbox{Sn}$ strand; superconducting coils;
  • fLanguage
    English
  • Journal_Title
    Applied Superconductivity, IEEE Transactions on
  • Publisher
    ieee
  • ISSN
    1051-8223
  • Type

    jour

  • DOI
    10.1109/TASC.2013.2244639
  • Filename
    6461392