Abstract
The effect of radial power distribution and low flow rate on critical heat flux (CHF) was investigated. In this study, based on the CHF experimental results of Columbia University, the research validated the feasibility of the subchannel analysis code CTF to predict CHF. The results show that CTF code using the EPRI empirical CHF correlation can predict the CHF experimental results well. Due to radially non-uniform power distribution, the quality and void fraction of hot subchannels are higher than other subchannels. The influence of the lateral flow will cause the counterflow in low power region under the beginning of two-phase flow at low flow rate. Furthermore, the predicted average CHF of rod assembly increases with the increase of inlet mass flow rate and the decrease of inlet temperature. When CHF happens in the rod assembly, the local CHF is mainly due to the low mass flow rate and high quality.
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