Regulatory Assessment of Effectiveness of ACR-1000 Emergency Core Cooling System
NURETH-14 - 2011 September 25-30

Presented at:
2011 September 25-30
Toronto, Canada
Session Title:
G3-1 Advanced PWRs, Advanced BWRs, Advanced CANDU Reactors

Aurelian Tanase (CNSC, University of Ottawa)
Robert Gibb (CNSC)
Aleksandar Delja (Canadian Nuclear Safety Commission)


The paper presents the regulatory approach for assessment of the Advanced CANDU Reactor (ACR)-1000 Large Loss of Coolant Accident (LOCA) Emergency Core Cooling (ECC) effectiveness, describes the rationale for the selection of sensitivity cases and discusses the results of the simulations for 50% Pump Suction Break (PSB). The separate in-house simulations strengthened the CNSC staff knowledge about the ACR-1000 design and the modeling methodology. The review of representation of plant systems and plant behavior indicated no major issues. The selected accident scenarios and the limited scope sensitivity cases conducted by the CNSC staff, indicated that, overall, the ECC performance showed small sensitivity to the parameters and assumptions considered for investigation.

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