CHF results of horizontally deposited rods under pool boiling conditions
收藏科学数据银行2025-10-22 更新2026-04-23 收录
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https://www.scidb.cn/detail?dataSetId=32940e5c5eec4575b872109af03b0ddb
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资源简介：
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.
提供机构：
Fudan University; Shanghai Jiao Tong University
创建时间：
2025-10-22
