A dataset of thermal striping at the reactor core outlet

This paper presents a dedicated dataset for the study of thermal striping in the reactor core outlet region. The dataset covers three working fluids: water, liquid sodium (Na), and liquid lead-bismuth eutectic (LBE), encompassing a variety of typical simplified  geometries and operating conditions. Each data entry fully records key boundary conditions, geometric parameters, characteristic reference scales, and measurement point layout information. The dataset also includes critical characteristic quantities, such as average and transient temperature, velocity parameters, temperature fluctuation intensity, and temperature power spectral density (PSD), which are applicable for model validation and pattern analysis. This dataset provides reliable, structured data support for the analysis of thermal striping mechanisms, validation of turbulent heat transfer models, and the development of data-driven predictive methods. It also offers valuable data references for the safety assessment and optimization of reactor thermal-hydraulic designs.