• DocumentCode
    3200322
  • Title

    Plasma facing conponents of EAST

  • Author

    Song, Y.T. ; Xie, H. ; Liu, X. ; Bao, L. ; Zhou, Z. ; Cao, L. ; Xu, T. ; Peng, X. ; Peng, Y. ; Zhu, N. ; Zhang, P. ; Wu, J. ; Wang, S. ; Wang, X. ; Hu, J. ; Chen, J. ; Luo, G. ; Yao, D. ; Gao, D. ; Fu, P. ; Li, J.

  • Author_Institution
    Inst. of Plasma Phys., Chinese Acad. of Sci., Hefei, China
  • fYear
    2009
  • fDate
    1-5 June 2009
  • Firstpage
    1
  • Lastpage
    4
  • Abstract
    EAST plasma facing components (PFCs) have the function of protecting the vacuum vessel, heating systems and diagnostic components from the plasma particles and heat loads, and also additional to this particles and heat loads handling. They are installed in the vacuum vessel together with in-vessel coils, cryopump and diagnostic components. The design, fabrication and assembly have been finished. The PFCs are designed up-down symmetry to accommodate with both double null and single null plasma configuration. All PFCs use graphite tile for plasma facing surfaces affixed to copper alloy heat sink. A special deep hole drilling technology was developed to drill cooling channels directly on heat sink for high efficient heat removal. All Heat sink are installed onto the base alignment rails through stainless steel supports. As the benchmark of assembly for PFCs, the base rails are installed and measured precise based on a new alignment method integrating the optical instruments and a mechanical template. And so is a mechanical check template for checking the surface of first wall. As indicated, all the first wall components were fabricated and assembled successfully and meet the design requirement for the plasma operation.
  • Keywords
    Tokamak devices; cooling; cryopumping; fusion reactor design; fusion reactor divertors; fusion reactor instrumentation; fusion reactor operation; heat sinks; plasma diagnostics; EAST plasma facing component design; PFC design; copper alloy heat sink; cryopump components; deep hole drilling technology; diagnostic components; double null plasma configuration; drill cooling channels; first wall components; graphite tile; heat loads; heating systems; in-vessel coils; mechanical templates; optical instruments; plasma operation; plasma particles; single null divertor plasma; single null plasma configuration; stainless steel supports; vacuum vessel; Assembly; Coils; Fabrication; Heat sinks; Heating; Plasma diagnostics; Plasma measurements; Protection; Rails; Vacuum systems; EAST; alignment; design; fabrication; plasma facing components;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 2009. SOFE 2009. 23rd IEEE/NPSS Symposium on
  • Conference_Location
    San Diego, CA
  • Print_ISBN
    978-1-4244-2635-5
  • Electronic_ISBN
    978-1-4244-2636-2
  • Type

    conf

  • DOI
    10.1109/FUSION.2009.5226435
  • Filename
    5226435