• DocumentCode
    3119996
  • Title

    Heat removal possibilities of nuclear containments during a severe accident

  • Author

    Lovasz, Liviusz ; Boros, Ildiko

  • Author_Institution
    Budapest Univ. of Technol. & Econ., Budapest, Hungary
  • fYear
    2013
  • fDate
    6-8 June 2013
  • Firstpage
    1
  • Lastpage
    5
  • Abstract
    After the accident in Fukushima the safety reviews of nuclear power plants showed several safety shortcomings. One of the identified problems is the long term depressurization of containment buildings, in case of a station blackout. A possible solution for the problem for VVER-440 type nuclear power plants was analyzed in the work: how heat exchangers placed in the containment can reduce the pressure. The analysis was made with the integral source term code ASTEC. To prove the effectiveness of heat exchangers, a containment model was built and different simulations - without heat exchangers or with heat exchanger installed at different locations inside the containment building - were run.. The plant specific parameters came from the Paks Nuclear Power Plant. The analysis proved the efficiency of heat exchangers for depressurization, but showed that their effect highly depends on the location they are built in.
  • Keywords
    fission reactor accidents; fission reactor containment; heat exchangers; nuclear power stations; ASTEC; Fukushima; Paks Nuclear Power Plant; VVER-440 type nuclear power plants; containment buildings; containment model; heat exchangers; heat removal possibilities; integral source term code; long term depressurization; nuclear containments; plant specific parameters; safety reviews; safety shortcomings; station blackout; Heating;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Energy (IYCE), 2013 4th International Youth Conference on
  • Conference_Location
    Sio??fok
  • Type

    conf

  • DOI
    10.1109/IYCE.2013.6604167
  • Filename
    6604167