Critical Heat Flux, Single-Phase and Two-Phase Pressure Drop Methodologies For CANFLEX-NU with Crept and Uncrept Pressure Tubes

Abstract

Methodologies were developed for pressure drop (single and two-phase), Onset of Significant Void and local conditions Critical Heat Flux applicable to crept and uncrept fuel channels containing 43-element CANFLEX Natural Uranium (NU) fuel bundles. The correlations are based on the Stern Laboratory Incorporated experimental data for CANFLEX NU design. To obtain the coefficients for the different correlations developed, the Gauss-Newton method for unconstrained optimization problems was employed. Excellent agreement was obtained between experimental data and the predictions of the developed correlations.