Development and Preliminary Validation of the Fine Fuel Cell Subchannel Analysis Code CUNLUN

Abstract In response to the low resolution caused by the assumption of homogenization in traditional subchannel analysis methods and the high computational resource consumption of computational fluid dynamics (CFD). This article proposes a novel subchannel calculation and analysis method for pressurized water reactor cores that combines the advantages of CFD and subchannel analysis methods, and develops a thermal hydraulic calculation and analysis code CUNLUN for pressurized water reactor cores based on this method using C++language. Preliminary verification was carried out with the numerical simulation results of ANSYS FLUENT, and the calculation results were basically consistent with the experimental data and FLUENT numerical simulation results, indicating that the code can improve the accuracy of predicting local thermal and hydraulic parameters in the subchannel of the pressurized water reactor core, and can predict the flow characteristics of the coolant in the pressurized water reactor core. This code can provide effective design and research methods for thermal hydraulic analysis of pressurized water reactor fuel assemblies.