• DocumentCode
    3172320
  • Title

    Fabrication and test of hydraulic jacks for the application to divertor support system of Fusion Experimental Reactor

  • Author

    Fukushima, H. ; Itoh, K. ; Ohmori, J. ; Miki, N. ; Tachikawa, N. ; Nishio, S. ; Koizumi, K. ; Okazaki, T. ; Shimizu, K.

  • Author_Institution
    Heavy Apparatus Eng. Lab., Toshiba Corp., Yokohama, Japan
  • fYear
    1991
  • fDate
    30 Sep-3 Oct 1991
  • Firstpage
    580
  • Abstract
    Two different types of hydraulic jacks, consisting of hydraulic piston and bellows were developed for an application to locking and lifting systems for divertor segments for the Fusion Experimental Reactor. For the lifting system where a minimum stroke of 170 mm was required, a telescopic-type hydraulic jack with a length of 300 mm was fabricated and tested under an operation pressure of 1 MPa. For the locking system, a hydraulic jack with a conical cotter was developed that worked at 6.5 MPa under a radial offset of 2 mm. These jacks satisfied their specifications without any leakage, failure, or abrasion. The performance of several hard facing materials for the cotter, including alumina and metal alloys, was also examined. The Colmonoy No. 5 or Stellite alloy No. 6 was found to be excellent as a hard facing material for the cotter
  • Keywords
    Tokamak devices; fusion reactor theory and design; Colmonoy; FER; Fusion Experimental Reactor; Stellite; alumina; bellows; conical cotter; divertor segments; hard facing materials; hydraulic jacks; hydraulic piston; locking system; metal alloys; Bellows; Fabrication; Fatigue; Inductors; Inorganic materials; Joining processes; Lifting equipment; Pistons; System testing; Welding;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 1991. Proceedings., 14th IEEE/NPSS Symposium on
  • Conference_Location
    San Diego, CA
  • Print_ISBN
    0-7803-0132-3
  • Type

    conf

  • DOI
    10.1109/FUSION.1991.218854
  • Filename
    218854