Computational Fluid Dynamics investigation of the impact of 6% crept pressure tubes on flow behaviour, fuel temperature, and pressure tube wall temperature of a single CANDU 37M fuel bundle

CANDU nuclear generating stations experience aging effects that affect the reactor operation, including pressure tube deformation ( i.e ., diametral expansion, sag, and elongation). The diametral expansion of the pressure tube will alter coolant flow behaviour, which will impact CANDU fuel and pressure tube temperatures, thereby directly affecting the reactor’s operational performance and safety margins. However, these impacts are not yet fully understood at this point. In this study, two Computational Fluid Dynamics simulations were conducted with STAR CCM+ on a single CANDU Modified 37-element (37M) fuel bundle placed in both non-crept and 6% crept pressure tubes under normal operating conditions. The predicted coolant flow behaviour, fuel temperatures, and pressure tube wall temperatures were compared between both cases to predict the impact of diametral expansion on these aspects. The results indicate that approximately 29% of the coolant flow bypasses the bundle in the 6% crept pressure tube, leading to a reduction of up to 25% in subchannel flow velocity and a maximum increase of 36.7 K in fuel maximum temperature. Both the non-crept and 6% crept pressure tube wall temperature profiles were found to be asymmetric with respect to the bundle’s horizontal axis. The temperature at the bottom of the pressure tube is relatively higher than at the top in the non-crept case, while the temperature difference is noticeably greater in the 6% crept case. • This work performed two CFD simulations with heat transfer on a CANDU 37M bundle. • This work predicted the fuel temperature for a bundle in non-crept and 6% crept PTs. • This work predicted the PT temperature for a bundle in non-crept and 6% crept PTs.