Abstract

Abstract The methodology and philosophy of hot channel factors and the analytical procedure in their application to the core thermal-hydraulic design of LMFBRs are discussed. The hot channel factors adopted in the calculation of fuel and blanket rod temperatures for the Clinch River Breeder Reactor are quantitatively presented; the experimental data base of some of the hot channel factors used in determination of maximum cladding temperature are discussed in detail. Power-to-melt uncertainties, introduced for the first time during the CRBRP design to assess the margin-to-incipient melting in fuel and blanket rods, are presented and quantitatively elaborated. The role of the hot channel factors on the overall core thermal-hydraulic design and extension of uncertainty analyses to calculations other than rod temperature are discussed along with recommendations for improvements in hot channel factors analyses.

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