• DocumentCode
    2053560
  • Title

    The breeding blanket interface (BBI) and the Tritium Systems Test Assembly (TSTA)

  • Author

    Anderson, J. ; Bartlit, J. ; Sherman, R. ; Sze, D.-K. ; Finn, P. ; Clemmer, R. ; Naruse, Y. ; Yoshida, H. ; Okuno, K. ; Enoeda, M.

  • Author_Institution
    Los Alamos Nat. Lab., NM, USA
  • fYear
    1989
  • fDate
    2-6 Oct 1989
  • Firstpage
    804
  • Abstract
    The Tritium Systems Test Assembly (TSTA) project at Los Alamos National Laboratory is charged with developing and demonstrating the fusion fuel processing requirement for the magnetic fusion energy program. The key fusion fuel streams are the plasma exhaust and the blanket stream. At present, the technology under development at TSTA includes only the plasma exhaust. The blanket is a logical upgrade to TSTA and the upgrade is the subject of an ongoing study. The program, called the Breeding Blanket Interface (BBI), is being investigated with the intention of installing such a processing system at TSTA in the 1992-1993 time frame. The BBI program was initiated in July, 1987. The conditions of the tritium product streams of various blankets were determined. Pre-conceptual designs of the BBI systems were developed for two blanket concepts: aqueous lithium salt solution blanket and solid breeder blanket. Preliminary estimates of costs have been performed and the schedule of the TSTA/BBI program has been developed. The schedule and planning of the TSTA/BBI program are discussed. The goal of the program is to establish the engineering data basis of the fuel cycle for an International Thermonuclear Engineering Reactor
  • Keywords
    fusion reactor fuel; tritium handling; BBI; International Thermonuclear Engineering Reactor; T; TSTA; Tritium Systems Test Assembly; aqueous lithium salt solution blanket; blanket stream; breeding blanket interface; fuel cycle; fusion fuel processing requirement; magnetic fusion energy program; plasma exhaust; solid breeder blanket; upgrade; Assembly systems; Costs; Data engineering; Fuels; Inductors; Laboratories; Lithium; Plasma materials processing; Solids; System testing;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 1989. Proceedings., IEEE Thirteenth Symposium on
  • Conference_Location
    Knoxville, TN
  • Type

    conf

  • DOI
    10.1109/FUSION.1989.102339
  • Filename
    102339