Clinch River Breeder Reactor Plant. Heat transfer correlation for analysis of CRBRP assemblies

An investigation was performed to assess the adequacy of the correlations currently used to describe the heat transfer coefficient to sodium flowing in CRBRP assemblies in light of the experimental data acquired after 1968. The available experimental data for bundles with P/D ratios of 1.05 to 1.3 and the relevant heat transfer correlations are described. Correlations for CRBR fuel, radial blanket and control assemblies are recommended.