• DocumentCode
    2062036
  • Title

    Alignment of the TFTR bumper limiter

  • Author

    Barnes, G.W. ; Owens, D.K. ; Loesser, G.D. ; Ulrickson, M.

  • Author_Institution
    Plasma Phys. Lab., Princeton Univ., NJ, USA
  • fYear
    1989
  • fDate
    2-6 Oct 1989
  • Firstpage
    937
  • Abstract
    The TFTR (Tokamak Fusion Test Reactor) bumper limiter (BL) is an axisymmetric toroidal limiter mounted on the inner wall of the vacuum vessel. It subtends 120° poloidally and has a surface area of 22 m 2. The plasma-facing surface consists of 1000 kg of graphite tiles mounted on water-cooled Inconel backing plates. During the initial installation in the Spring of 1985, the limiter surface was aligned to the toroidal magnetic field by mechanical and magnetic measurements to an estimated accuracy of ±2 mm. The methods used to mechanically align the limiter are described, and evidence, based on machine operation with a plasma, that the limiter is reasonably well aligned with the toroidal field is presented. Future work addressing the alignment of the total limiter to the toroidal field using mechanical and magnetic measurements and the replacement of a subset of the carbon times with carbon-carbon composite material is also discussed
  • Keywords
    Tokamak devices; fusion reactor materials; fusion reactor theory and design; 1000 kg; C; C-C composite; Ni-Cr; TFTR; Tokamak Fusion Test Reactor; axisymmetric toroidal limiter; bumper limiter; graphite tiles; plasma-facing surface; toroidal field; water-cooled Inconel backing plates; Composite materials; Inductors; Magnetic variables measurement; Plasma materials processing; Plasma measurements; Springs; Testing; Tiles; Tokamaks; Toroidal magnetic fields;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 1989. Proceedings., IEEE Thirteenth Symposium on
  • Conference_Location
    Knoxville, TN
  • Type

    conf

  • DOI
    10.1109/FUSION.1989.102371
  • Filename
    102371