• DocumentCode
    2929524
  • Title

    Engineering overview of the ITER hybrid central solenoid

  • Author

    Heitzenroeder, P. ; Brooks, A. ; Citrolo, J. ; Dahlgren, F. ; Neilson, H. ; Montgomery, D.B. ; Sborchia, C.

  • Author_Institution
    Plasma Phys. Lab., Princeton Univ., NJ, USA
  • Volume
    2
  • fYear
    1997
  • fDate
    6-10 Oct 1997
  • Firstpage
    693
  • Abstract
    The hybrid central solenoid was proposed as a possible alternative to the segmented central solenoid since it avoids the most serious issue of the segmented solenoid design: the placement of superconducting joints in a 13 T field. The hybrid is so named because it adopts features from both the reference and segmented designs in a configuration which results in the fields at the superconducting joints being similar to those in the reference design. This paper overviews the engineering details of the reference, segmented, and hybrid designs and discusses the tradeoffs involved in the various designs. Although the hybrid was not adopted for the EDA design due to unresolved issues, it evolved into the present reference design which includes some of the design details of the hybrid
  • Keywords
    Tokamak devices; fusion reactor design; superconducting magnets; ITER hybrid central solenoid; reference central solenoid configuration; segmented central solenoid; segmented solenoid concept; superconducting joints; Boring; Conductors; Manufacturing; Materials testing; Physics; Plasmas; Solenoids; Superconducting coils; Superconducting epitaxial layers; Wounds;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 1997. 17th IEEE/NPSS Symposium
  • Conference_Location
    San Diego, CA
  • Print_ISBN
    0-7803-4226-7
  • Type

    conf

  • DOI
    10.1109/FUSION.1997.687721
  • Filename
    687721