• DocumentCode
    2038877
  • Title

    Graphite as a plasma-facing material in fusion experiments

  • Author

    Langley, R.A.

  • Author_Institution
    Oak Ridge Nat. Lab., TN, USA
  • fYear
    1989
  • fDate
    2-6 Oct 1989
  • Firstpage
    522
  • Abstract
    The four major processes involved in hydrogen retention in graphite are reviewed. These processes are saturation of the near-surface region, diffusion on surface-connected porosity, intragranular diffusion, and erosion of carbon with concomitant formation of codeposited hydrogen-carbon films. It is suggested that in the retention of tritium in a fusion experiment the fourth process will dominate; therefore, from that point of view, it is the most important. To address the question of plasma fuel purity, more data are needed on ion-induced release of hydrogen isotopes by hydrogen isotopes and by heavier ions (e.g. carbon and oxygen) as a function of temperature
  • Keywords
    fusion reactor materials; graphite; C; fusion experiment; graphite; intragranular diffusion; ion-induced release; near-surface region; plasma fuel purity; surface-connected porosity; Anisotropic magnetoresistance; Gases; Heat pumps; Hydrogen; Magnetic materials; Plasma devices; Plasma materials processing; Plasma properties; Plasma temperature; Thermal resistance;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 1989. Proceedings., IEEE Thirteenth Symposium on
  • Conference_Location
    Knoxville, TN
  • Type

    conf

  • DOI
    10.1109/FUSION.1989.102274
  • Filename
    102274