TUF Validation Against Reactor Trip Data at Darlington NGS

Abstract

The physical parameters in the reactor controller, reactor physics and thermal-hydraulics models of the TUF code, associated with a reactor trip event are discussed in detail. To check the realism and the fidelity of the TUF performance, the prediction of a reactor trip event is compared with the plant data at Darlington NGS. The prediction of the system parameters is in reasonable agreement with the plant data. This simulation demonstrates the overall code performance in the operational support analysis for CANDU reactors.