• DocumentCode
    2342270
  • Title

    Rod Ejection Accident 3D-dynamic analysis in trillo NPP with RELAP5/PARCS V2.7

  • Author

    Barrachina, T. ; Miró, R. ; Verdu, G. ; Ortego, A. ; Martínez-Murillo, J.C.

  • Author_Institution
    Inst. Inst. for Ind., Radiophys. & Environ. Safety (ISIRYM), Univ. Politec. de Valencia (UPV), Valencia, Spain
  • fYear
    2010
  • fDate
    21-24 March 2010
  • Firstpage
    1
  • Lastpage
    7
  • Abstract
    The Rod Ejection Accident (REA) belongs to the Reactivity-Initiated Accidents (RIA) category of accidents, and it is part of the licensing basis accident analyses required for pressurized water reactors (PWR). The REA consist of a rod ejection due to the failure of its driving mechanism. The evolution is driven by a continuous reactivity insertion. In the present work, we have analyzed this transient in Trillo NPP at different power conditions at the beginning of cycle (BOC) and at the end of cycle (EOC) using the coupled code RELAP5MOD3.3/PARCSv2.7. The transient departs from an initially critical core, being the ejection speed of the control rod a typical bounding value. The simulation includes the SCRAM signal in order to compare our best-estimate results with the results from the conservative calculations provided by the NPP. These analyses will allow knowing more accurately characterize the PWR real plant phenomenology in the RIA most limiting conditions, in this way the conclusions will be realistic. The aim is to improve the understanding of these accidents using advanced methods.
  • Keywords
    fission reactor accidents; light water reactors; nuclear engineering computing; reactivity (fission reactors); 3D-dynamic analysis; PARCS V2.7; RELAP5-MOD3.3; SCRAM signal; Trillo NPP; continuous reactivity insertion; control rod; critical core; ejection speed; power conditions; pressurized water reactors; reactivity-initiated accidents; rod ejection accident; Analytical models; Fuels; Inductors; Industrial accidents; Licenses; Pressure control; Renewable energy resources; Safety; Temperature; Transient analysis;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Nuclear & Renewable Energy Conference (INREC), 2010 1st International
  • Conference_Location
    Amman
  • Print_ISBN
    978-1-4244-5213-2
  • Electronic_ISBN
    978-1-4244-5214-9
  • Type

    conf

  • DOI
    10.1109/INREC.2010.5462563
  • Filename
    5462563