• DocumentCode
    731638
  • Title

    Extension of the MELCOR code for analysis of late in-vessel phase of a severe accident

  • Author

    Dietrich, P. ; Kretzschmar, F. ; Miassoedov, A. ; Class, A. ; Villanueva, W. ; Bechta, S.

  • Author_Institution
    Karlsruhe Inst. of Technol. (KIT), Eggenstein-Leopoldshafen, Germany
  • fYear
    2015
  • fDate
    27-30 May 2015
  • Firstpage
    1
  • Lastpage
    8
  • Abstract
    The simulation of severe accidents in nuclear power plants with system codes is a powerful tool to improve the safety measures to prevent severe accidents. The further development of severe accident codes is part of current research. MELCOR, as the leading nuclear safety code, provides the possibility to be coupled to other codes. A detailed knowledge of this coupling interface is necessary to use this possibility. Therefore, the software tool DINAMO, which contains the coupling routines and an interface to communicate with other programs, was developed. Using DINAMO it is possible to utilize new models for specific phenomena in MELCOR. In the present work the Phase-Change Effective Convectivity Model was coupled using the CFD-software OpenFOAM and DINAMO to MELCOR to improve the prediction of molten core material in the lower plenum of a reactor pressure vessel. The simulation results were compared to the experimental findings of the LIVE-facility.
  • Keywords
    fission reactor accidents; fission reactor core control; nuclear engineering computing; pressure vessels; CFD-software OpenFOAM; DINAMO coupling routine; LIVE-facility; MELCOR code extension; coupling interface; molten core material prediction; nuclear power plant accident simulation; nuclear safety code; phase-change effective convectivity model; reactor pressure vessel plenum; severe accident code development; severe accident late in-vessel phase analysis; severe accident prevention; software tool; system code; Accidents; Coolants; Couplings; Heating; Mathematical model; Power generation; Safety; LIVE; MELCOR; PECM; core melt; coupled codes; in-vessel retention; nuclear safety;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Energy (IYCE), 2015 5th International Youth Conference on
  • Conference_Location
    Pisa
  • Print_ISBN
    978-1-4673-7171-1
  • Type

    conf

  • DOI
    10.1109/IYCE.2015.7180747
  • Filename
    7180747