Critical Heat Flux Datasets under Uniform and Non-Uniform Axial Heating Conditions [KAERI/TR-1665/2000]

The source of the data collected comes from the KAERI technical report [1]. The report includes an extensive set of experimental CHF measurements under both uniform and non-uniform heating conditions, providing valuable data for understanding and modeling CHF behavior in nuclear thermal-hydraulic systems. 

Overall, 1539 CHF test cases were collected/digitized from [1], comprising 651 uniform‐heating measurements and 888 non-uniform heating cases. The experimental setups used water coolant in round tubes with internal diameter of 5.44 - 28.3 mm and heated lengths of 0.061 - 7.0 m.

[1] C. PARK, “Effect of Axial Heat Flux Distribution on Critical Heat Flux,” Tech. Rep. KAERI/TR-1665/2000, Korea Atomic Energy Research Institute, Daejeon, Republic of Korea (October 2000).

Version 2 fixes several issues with the data coollection errors in KAERI technical report [1]. The non-uniform data were updated in accordance with the initial sources.