• DocumentCode
    161338
  • Title

    Validation of the TRACE code using PSB-VVER experiments

  • Author

    Blaha, M.

  • Author_Institution
    TES s.r.o., Třebíč, Czech Republic
  • fYear
    2014
  • fDate
    12-14 May 2014
  • Firstpage
    699
  • Lastpage
    704
  • Abstract
    The TRACE code is a new component-oriented reactor system analysis code designed to analyze light water reactor transients up to the point of significant fuel damage. The TRACE code is the latest in a series of advanced codes developed under the guarantee of U.S. NRC in frame of CAMP (Code Application and Maintenance Program). So the original code validation of the TRACE code was based on experiments performed on experimental facilities of typical PWR design. There are significant differences between PWR and VVER technologies. Therefore the TRACE code validation focused on VVER specific features was expected before its utilization in area of safety analyses in the Czech Republic. The TRACE code validation process is introduced specifically for VVER design using PSB-VVER integral test facility data and real plant data. The selected main results of the TRACE code specific validation are then presented against the PSB-VVER facility LB LOCA experimental test.
  • Keywords
    fission reactor safety; light water reactors; power system transients; CAMP; Czech Republic; LB LOCA experimental test; PSB-VVER experiments; PWR design; TRACE code validation; U.S. NRC; code application and maintenance program; component-oriented reactor system analysis; light water reactor transients; safety analysis; Coolants; Fuels; Generators; Inductors; Solid modeling; Test facilities; Transient analysis; LOCA; PSB; TRACE; VVER; code; validation;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Electric Power Engineering (EPE), Proccedings of the 2014 15th International Scientific Conference on
  • Conference_Location
    Brno
  • Type

    conf

  • DOI
    10.1109/EPE.2014.6839470
  • Filename
    6839470