SEVERE ACCIDENT ANALYSIS OF A SMALL LOCA ACCIDENT USING MAAP-CANDU TO SUPPORT LEVEL 2 PSA FOR THE POINT LEPREAU STATION REFURBISHMENT PROJECT
33rd Annual CNS Conference - 2012 June 10-13


Presented at:
33rd Annual CNS Conference
2012 June 10-13
Location:
Saskatoon, Canada
Session Title:
Safety & Licensing-2

Authors:
Sergei M. Petoukhov (Atomic Energy of Canada Limited)
Morgan J. Brown (Atomic Energy of Canada Limited)
P.M Mathew (Atomic Energy of Canada Limited)
  

Abstract

A Level 2 Probabilistic Safety Assessment was performed for the Point Lepreau Generating Station. The MAAP4-CANDU code was used to calculate the progression of postulated severe core damage accidents and fission product releases. Five representative severe core damage accidents were selected: Station Blackout, Small Loss-of-Coolant Accident, Stagnation Feeder Break, Steam Generator Tube Rupture, and Shutdown State Accident. Analysis results (timing of major events, hydrogen generation and fission product releases to the environment) for the reference SLOCA scenario are discussed in this paper.

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