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 …