• DocumentCode
    1098272
  • Title

    Installation and Test Programme of the ITER Poloidal Field Conductor Insert (PFCI) in the ITER Test Facility at JAEA Naka

  • Author

    Nunoya, Yoshihiko ; Takahashi, Yoshikazu ; Hamada, Kazuya ; Isono, Takaaki ; Matsui, Kunihiro ; Oshikiri, Masayuki ; Nabara, Yoshihiro ; Hemmi, Tsutomu ; Nakajima, Hideo ; Kawano, Katsumi ; Tsutsumi, Fumiaki ; Takano, Katsutoshi ; Uno, Yasuhiro ; Koizumi,

  • Author_Institution
    Japan Atomic Energy Agency (JAEA), Naka, Japan
  • Volume
    19
  • Issue
    3
  • fYear
    2009
  • fDate
    6/1/2009 12:00:00 AM
  • Firstpage
    1492
  • Lastpage
    1495
  • Abstract
    ITER PFCI has been manufactured in the Europe and installed into the ITER Test Facility in Naka, Japan. The conductor is NbTi cable-in-conduit conductor with thick square stainless steel jacket and almost identical with the design of the ITER PF coils. The main objective of this test is the characterization of the conductor and joints at the conditions relevant to the ITER PF coil operation. Intermediate joint is located in the winding at relatively high field to examine its performance. The main items in the PFCI test program are thermo-hydraulic test, DC mode test, cyclic test and pulse mode test. The PFCI and CSMC were successfully cooled down to cryogenic temperature within 450 hours. The test of the PFCI was performed from May to August 2008. The key technology of the installation, the test methods and procedures, and some preliminary results of cool-down are described in this paper.
  • Keywords
    Tokamak devices; electric conduits; fusion reactor design; fusion reactor materials; fusion reactor operation; niobium alloys; superconducting cables; superconducting coils; superconducting materials; titanium alloys; DC mode test; ITER PF coil design; ITER PF coil operation; ITER PFCI; ITER poloidal field conductor insert; cable-in-conduit conductor; cryogenic temperature; pulse mode test; square stainless steel jacket; thermohydraulic test; CS model coil; NbTi CICC; current sharing temperature; poloidal field coil;
  • fLanguage
    English
  • Journal_Title
    Applied Superconductivity, IEEE Transactions on
  • Publisher
    ieee
  • ISSN
    1051-8223
  • Type

    jour

  • DOI
    10.1109/TASC.2009.2019551
  • Filename
    5109608