[en] The Loss-of-Fluid Test (LOFT) facility contains a pressurized water nuclear reactor designed to scale the nuclear, thermal-hydraulic phenomena which would take place in a large pressurized water reactor (PWR) during a hypothetical loss-of-coolant accident (LOCA). This summary describes the development of a carryover rate fraction (CRF) correlation suitable for use in an evaluation model calculation for the reflooding phase of a LOFT experiment as well as the 3.6576-m core skewed axial power shape case. The CRF is defined as the ratio of mass rate entrained out of the core to the mass rate into the core