Abstract
Data from steady-state tests in the ThermalHydraulic Out-of-Reactor Safety (THORS) facility, a large loop for testing simulated liquid metal fast breeder reactor fuel bundles at Oak Ridge National Laboratory, were examined to determine whether the results from tests at similar conditions in the same bundle are reproducible. Comparisons of different tests at similar powers and coolant flows were made for several THORS bundles. The results show that the data were in fact reproducible and can be used with confidence by analysts to quantify computer codes and models.
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