• DocumentCode
    2027944
  • Title

    Safety analysis of potential loss of vacuum incident in JET

  • Author

    Wykes, M.E.P.

  • Author_Institution
    JET Joint Undertaking, Abingdon, UK
  • fYear
    1989
  • fDate
    2-6 Oct 1989
  • Firstpage
    312
  • Lastpage
    315
  • Abstract
    During plasma discharges, the graphite first-wall tiles of the JET (Joint European Torus) will be subjected to high thermal fluxes and consequent high temperatures. Accidental loss of vacuum through air inleakage in such a situation could cause graphite oxidation and concomitant energy input to the inleaking gas. The JET Exhaust Detritiation System (EDS) is designed to prevent the escape of tritiated gases and activated or toxic dust from the torus by pumping the breached torus to maintain a slightly subatmospheric pressure. A safety analysis is presented to verify that the design pumping capacity of the EDS is adequate to address the peak graphite oxidation rates envisaged during a potential air inleakage incident with hot graphite in the JET
  • Keywords
    accidents; fusion reactor materials; fusion reactor safety; graphite; plasma confinement; tritium handling; Exhaust Detritiation System; JET; Joint European Torus; concomitant energy input; design pumping capacity; graphite first-wall tiles; graphite oxidation; high thermal fluxes; plasma discharges; potential loss of vacuum incident; safety analysis; toxic dust; tritiated gases; Air safety; Elementary particle vacuum; Gases; Heat transfer; Helium; Oxidation; Plasma temperature; Protection; Tiles; Upper bound;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 1989. Proceedings., IEEE Thirteenth Symposium on
  • Conference_Location
    Knoxville, TN
  • Type

    conf

  • DOI
    10.1109/FUSION.1989.102229
  • Filename
    102229