• DocumentCode
    298212
  • Title

    Extended operation of reactor-scale fusion fuel loop under US-Japan collaboration

  • Author

    Konishi, S. ; Hayashi, T. ; Yamanishi, T. ; Nakamura, H. ; Naruse, Y. ; Okuno, K. ; Sherman, R.H. ; Willms, R.S. ; Barnes, J.W. ; Bartlit, J.R. ; Anderson, J.L.

  • Author_Institution
    JAERI, Ibaraki, Japan
  • Volume
    1
  • fYear
    1993
  • fDate
    11-15 Oct 1993
  • Firstpage
    204
  • Abstract
    Tritium Systems Test Assembly (TSTA) in the Los Alamos National Laboratory is a reactor-scale fusion fuel processing loop and is operated by the Japan Atomic Energy Research Institute (JAERI) and the USDOE under the collaboration. An extended experimental campaign of the TSTA loop was performed with 100 grams of tritium in April-May 1992 in order to simulate a steady-state fusion fuel processing for 25 days. Continuous processing of simulated plasma exhaust (DT and H mixture, He, CH4 and N2) was successfully demonstrated. Impurity processing was successfully tested by two different techniques. US developed Fuel Cleanup System (FCU) purifies DT by cryogenic molecular sieve beds and decomposes tritiated water by Magnesium beds. Japanese developed J-FCU is based on purification by permeation through palladium alloy membrane and vapor electrolysis with a ceramic electrolyte cell. Isotope Separation System was stably operated with four interlinked columns and continuously produced pure tritium and deuterium stream while exhausting protium impurity. Real-time analysis in the ISS process was demonstrated with the laser Raman Spectroscopy. The result demonstrated the safe and stable operation of reactor-scale fusion fuel loop in a steady state
  • Keywords
    fusion reactor fuel; isotope separation; low-temperature techniques; 100 g; CH4; DT; DT purification; H; He; Isotope Separation System; Magnesium beds; N2; Pd alloy membrane; TSTA; Tritium Systems Test Assembly; ceramic electrolyte cell; cryogenic molecular sieve beds; impurity processing; laser Raman Spectroscopy; permeation purification; protium impurity; reactor-scale fusion fuel loop; reactor-scale fusion fuel processing loop; real-time analysis; simulated plasma exhaust; tritiated water decomposition; tritium; vapor electrolysis; Assembly systems; Collaboration; Fuels; Helium; Impurities; Laboratories; Plasma materials processing; Plasma simulation; Steady-state; System testing;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 1993., 15th IEEE/NPSS Symposium on
  • Conference_Location
    Hyannis, MA
  • Print_ISBN
    0-7803-1412-3
  • Type

    conf

  • DOI
    10.1109/FUSION.1993.518315
  • Filename
    518315