Thermalhydraulic studies in support of qualification of low-void reactivity fuel

Previous thermalhydraulic studies on critical heat flux, post-dryout heat transfer and fuel string pressure drop for CANFLEX®. bundles have been assessed for their applicability in the qualification of the low void-reactivity fuel (LVRF) bundle to be used in the Bruce Nuclear Generation Station. Large amounts of experimental data were obtained covering reference bundle and channel geometries, as well as separate effects on thermalhydraulic parameters. Prediction methods derived with these data are directly applicable in critical channel power and safety analyses for the LVRF bundle. Minor differences between LVRF and test bundle designs have little impact on these thermalhydraulic parameters. Several experiments have been completed to provide confirmatory data on critical heat flux and post-dryout heat transfer in support of the LVRF qualification program. A pressure-drop experiment is currently in progress to obtain hydraulic information on the LVRF bundle.