• DocumentCode
    2554924
  • Title

    TPX in-vessel remote maintenance tooling

  • Author

    Rennich, M.J. ; Silke, G.W.

  • Author_Institution
    Oak Ridge Nat. Lab., TN, USA
  • Volume
    2
  • fYear
    1995
  • fDate
    30 Sep-5 Oct 1995
  • Firstpage
    1367
  • Abstract
    The Tokamak Physics Experiment (TPX) has used the lessons learned from successful remote maintenance and remote handling facilities to develop both a concept and philosophy for incorporation of remote design from the earliest phases of the project. Initiation of mockup testing during the conceptual design phase leads to significant improvements in the basic maintenance equipment configuration. In addition, remote handling features and capabilities have been incorporated into the design of the plasma-facing components (PFCs) as part of the total PFC design effort
  • Keywords
    Tokamak devices; fusion reactor operation; nuclear reactor maintenance; telecontrol; TPX in-vessel remote maintenance tooling; Tokamak Physics Experiment; basic maintenance equipment configuration; plasma-facing components; remote handling facilities; remote handling features; Fusion power generation; Laboratories; Physics; Plasma diagnostics; Rails; Remote handling; Testing; Tokamaks; Vehicles; Water pollution;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 1995. SOFE '95. Seeking a New Energy Era., 16th IEEE/NPSS Symposium
  • Conference_Location
    Champaign, IL
  • Print_ISBN
    0-7803-2969-4
  • Type

    conf

  • DOI
    10.1109/FUSION.1995.534482
  • Filename
    534482