Assessment of nucleate boiling correlations applied to thermal-hydraulic code of reactor

This article is set in development of reactor thermal-hydraulic analysis code-COSINE, studies variation characteristic of results of nucleate boiling correlations usually used for thermal-hydraulic analysis codes with variable changing, compares difference degree of different correlations and sensitivity in different ranges based on fuel rod wall heat transfer and external reactor vessel coolant conditions, in order to provide advice on setting of code user options and further experiment researches. It draws a conclusion that the condition of high superheat degree is mostly needed experimental demonstration and Chen, Schrock-Grossman1, Wright and Schrock-Grossman2 correlations are more suitable for calculating these conditions in reactor thermal-hydraulic analysis code. (authors)