CHF results of horizontally deposited rods under pool boiling conditions

This dataset provides experimental results of critical heat flux (CHF) for horizontal deposition rods. CHF is a key parameter in nuclear reactor safety and thermal-hydraulic analysis. The data includes CHF values under various working conditions (different deposition particle concentrations and diameters), which can be used to study heat transfer limits and boiling crisis phenomena in nuclear fuel rod applications. This dataset aims to enhance the understanding of CHF mechanisms and support the validation of thermal-hydraulic models for reactor design and safety assessment.