• DocumentCode
    1948876
  • Title

    Space reservation for the peripheral components of W7-X

  • Author

    Renard, S. ; Baylard, Ch ; Hartmann, D.

  • Author_Institution
    Inst. for Magn. Fusion Res. (IRFM), CEA Cadarache, St. Paul-lez-Durance, France
  • fYear
    2011
  • fDate
    26-30 June 2011
  • Firstpage
    1
  • Lastpage
    6
  • Abstract
    Wendelstein 7-X (W7-X) is a fusion device of the stellarator type with optimized magnetic field geometry and superconducting coils. The scientific goals of W7-X are to confirm the predicted improvement of the plasma confinement and to demonstrate the technical suitability of such a device as a fusion reactor. It is presently under construction at the Max Planck Institute for Plasma Physics (IPP) in Greifswald, Germany. The W7-X machine requires numerous peripheral components such as plasma heating systems, diagnostics, vacuum and cryogenic distributions, water cooling circuits, cable trays and electronics racks. These represent more than 6000 components which will be installed by 2014 in the experiment hall. The extreme complexity of the machine and the (too) small size of the experiment hall require a rigorous management of the space allocated to each component. The space-constrained environment also causes significant challenges in the maintenance scheme of the components. For these reasons, the concept of “Space Reservation” was implemented through CAD models. These take into account the specific maintenance needs and the geometrical tolerances of the components. The aims were: rationalize design processes and minimize iterations in spite of concurrent engineering issues. In this paper, the definition of the component and maintenance spaces will be explained as well as the methodology to manage the conflicts between them. A sampling of different components, their maintenance spaces and their specific needs will be presented to illustrate the challenges posed for the design, the maintenance tools and the assembly procedure.
  • Keywords
    Tokamak devices; fusion reactor materials; nuclear electronics; plasma diagnostics; plasma heating; plasma toroidal confinement; superconducting coils; CAD models; W7-X machine; Wendelstein 7-X; assembly procedure; cable trays; cryogenic distribution; electronics racks; fusion device; fusion reactor; geometrical tolerances; magnetic field geometry; maintenance spaces; maintenance tools; peripheral components; plasma confinement; plasma diagnostics; plasma heating systems; space reservation; space-constrained environment; superconducting coils; vacuum distribution; water cooling circuits; layout; maintenance; space reservation;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering (SOFE), 2011 IEEE/NPSS 24th Symposium on
  • Conference_Location
    Chicago, IL
  • ISSN
    1078-8891
  • Print_ISBN
    978-1-4577-0669-1
  • Electronic_ISBN
    1078-8891
  • Type

    conf

  • DOI
    10.1109/SOFE.2011.6052274
  • Filename
    6052274