2026-10-14T21:58:28Z https://www.scidb.cn/oai

10.57760/sciencedb.hjs.00506 2025-10-23T11:50:27Z

2025-10-23 CHF results of horizontally deposited rods under pool boiling conditions doi:10.57760/sciencedb.hjs.00506 en 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. Pool boiling experiment; Particle deposition; Critical heat flux Wang Xiaowen Liu Maolong Cong Tenglong Xiao Yao Gu Hanyang PUBLIC https://creativecommons.org/licenses/by-nc/4.0/ dataset http://www.doi.org/10.3724/j.0253-3219.2026.hjs.49.250263 Science Data Bank