• DocumentCode
    65970
  • Title

    Qualification of the ITER Correction Coils and Their Conductor

  • Author

    Li, Huaqing ; Luo, Dan ; Wang, Michael ; Wu, Wenchuan ; Liu, B. ; Wei, Jason ; Wu, Yaowu ; Li, Jie ; Qin, Jiahu ; Libeyre, P. ; Devred, Arnaud ; Mitchell, Neil

  • Author_Institution
    China Int. Nucl. Fusion Energy Program Execution Center, Beijing, China
  • Volume
    24
  • Issue
    3
  • fYear
    2014
  • fDate
    Jun-14
  • Firstpage
    1
  • Lastpage
    4
  • Abstract
    The ITER correction coils (CCs) are designed to be arranged toroidally around the machine inside the poloidal field coils and mounted on the toroidal field coils in order to compensate field errors arising from misalignment of the coils and winding deviations from the nominal shape as a result of fabrication tolerances, joints, leads, busbars CCs, and assembly tolerances. China is responsible for manufacturing all the CCs and their conductor. The paper presents the qualification progress and results of ITER CCs and CC conductor, including the test results of CC SULTAN samples, double pancakes winding experiments, CC case welding techniques, and manufacturing experiment of CC helium inlet/outlets.
  • Keywords
    Tokamak devices; plasma toroidal confinement; superconducting coils; ITER correction coils; assembly tolerances; coil misalignment; fabrication tolerances; poloidal field coils; toroidal field coils; Coils; Conductors; Insulation; Qualifications; Welding; Windings; Conductor; NbTi; correction coil (CC); qualification;
  • fLanguage
    English
  • Journal_Title
    Applied Superconductivity, IEEE Transactions on
  • Publisher
    ieee
  • ISSN
    1051-8223
  • Type

    jour

  • DOI
    10.1109/TASC.2013.2286677
  • Filename
    6646264