Numerical Investigations of the LBE Flow and Heat Transfer Characteristics in the Helical-Coiled Tube Bundle

Due to the advantages of compactness and enhanced heat transfer efficiency, the Helical-Coiled Once-Through Steam Generator (HCOTSG) is one of the best choices to be applied in the Lead-bismuth Fast Reactor (LFR). In order to investigate the flow and heat transfer characteristics in the shell side of lead-bismuth eutectic (LBE) HCOTSG for the purpose of safety analysis and optimization design, a CFD method for calculating the heat transfer and flow resistance in helical-coiled tube bundles is proposed. Based on available relevant experimental studies, the numerical model is validated. Validation results indicate that the liquid LBE cross flow through helical-coiled tube bundles can be well simulated using SST k-ω model and turbulent Prandtl number model. The maximum deviation for both friction factor and Nusselt number is less than 15%. After validating the reliability of the numerical model, geometry models with different helix angles of the shell side are established. Effects of helix angle on the flow resistance and heat transfer performances are presented. The flow and heat transfer characteristics in the helical-coiled tube bundle are numerically simulated and analyzed. This work provides a new method for studying the flow and heat transfer characteristics and optimization design of liquid metal H-OTSG.