• DocumentCode
    41871
  • Title

    Conceptual Design of the CFETR Toroidal Field Superconducting Coils

  • Author

    Zheng, J.X. ; Song, Y.T. ; Liu, X.F. ; Li, J.G. ; Wan, Y.X. ; Wan, B.N. ; Lei, M.Z. ; Zhu, C.X. ; Kang, R. ; Khan, S.U.

  • Author_Institution
    Inst. of Plasma Phys., Hefei, China
  • Volume
    25
  • Issue
    2
  • fYear
    2015
  • fDate
    Apr-15
  • Firstpage
    1
  • Lastpage
    9
  • Abstract
    The China Fusion Engineering Test Reactor (CFETR) superconducting tokamak is a national scientific research project of China with plasma major and minor radii of 5.7 and 1.6 m, respectively. The magnetic field in the center of plasma at a radius of R = 5.7 m is 5.0 T. The major objective of the project is to build a fusion engineering tokamak reactor with fusion power within the range of 50-200 MW and should be self-sufficient by blanket. Sixteen toroidal field (TF) superconducting coils of CFETR have been arrayed toroidally and are made up of Nb3Sn superconductor. The maximum magnetic field of the TF coil is 10.8 T under the operation current of 67.4 kA. The TF coil should have strong stability margin under the condition of high field and strain. This paper discusses the design parameters, electromagnetic distribution, structure, and thermal and stability analysis of the TF superconducting magnet for CFETR.
  • Keywords
    Tokamak devices; niobium alloys; superconducting coils; superconducting critical field; superconducting magnets; thermal stability; tin alloys; type II superconductors; CFETR toroidal field superconducting coils; China Fusion Engineering Test Reactor; Nb3Sn; current 67.4 kA; electromagnetic distribution; fusion engineering tokamak reactor; fusion power; magnetic field; magnetic flux density 10.8 T; national scientific research project; plasma center; power 50 MW to 200 MW; superconducting magnet; superconducting tokamak; thermal stability analysis; Conductors; Magnetic fields; Plasmas; Superconducting cables; Superconducting coils; Superconducting magnets; CFETR; China Fusion Engineering Test Reactor (CFETR); magnet; superconducting; toroidal field; toroidal field (TF);
  • fLanguage
    English
  • Journal_Title
    Applied Superconductivity, IEEE Transactions on
  • Publisher
    ieee
  • ISSN
    1051-8223
  • Type

    jour

  • DOI
    10.1109/TASC.2015.2396942
  • Filename
    7027224