• DocumentCode
    300953
  • Title

    Fusion safety experiments in JAERI

  • Author

    Kunugi, T. ; Takase, K. ; Ogawa, M. ; Seki, Y.

  • Author_Institution
    JAERI, Ibaraki, Japan
  • Volume
    1
  • fYear
    1995
  • fDate
    30 Sep-5 Oct 1995
  • Firstpage
    313
  • Abstract
    Two experimental studies for the thermal-hydraulic safety of fusion reactors, ingress of the coolant events (ICE) and loss of vacuum events (LOVA), have been started as ITER safety sub-tasks for three years since February, 1995. In these researches, as for the ICE experiments, the preliminary ICE apparatus has been completed by the end of September, 1995. On the other hand, as for the LOVA experiments, the preliminary LOVA apparatus that simulated a vacuum vessel of the fusion reactor with a small-scaled model has already been constructed. The buoyancy-driven exchange flow behavior through breaches between the inside (filled with helium gas) and the outside (i.e., air) of the apparatus under the LOVA condition was investigated quantitatively. This paper summarizes the outline of the preliminary ICE and LOVA apparatuses, their experimental contents and research schedules
  • Keywords
    Tokamak devices; fusion reactor safety; plasma toroidal confinement; ICE; ITER safety sub-tasks; JAERI; LOVA; buoyancy-driven exchange flow behavior; fusion safety experiments; ingress of the coolant events; loss of vacuum events; thermal-hydraulic safety; vacuum vessel; Heat transfer; Ice; Plasma materials processing; Plasma measurements; Plasma temperature; Plasma waves; Pressure measurement; Safety; Size measurement; Water heating;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Fusion Engineering, 1995. SOFE '95. Seeking a New Energy Era., 16th IEEE/NPSS Symposium
  • Conference_Location
    Champaign, IL
  • Print_ISBN
    0-7803-2969-4
  • Type

    conf

  • DOI
    10.1109/FUSION.1995.534230
  • Filename
    534230