An analytical expression for counter current flow limitation (CCFL) was used to predict critical heat flux (CHF) for downward flow in thin vertical rectangular channels which are prototypes of coolant channels in test and research nuclear reactors. Top flooding is the mechanism for counter-current flow limited CHF. The CCFL correlation also was used to determine the circulation and flooding-limited CHF. Good agreements were observed between the period the model predictions and data on the CHF for downflow. The minimum CHF for downflow is lower than the flooding-limited CHF and it is predicted to occur at a liquid flow rate higher than that at the flooding limit.
Presented at the 13th ASME-JSME International Solar Energy Conference
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- Channel Flow;
- Flow Velocity;
- Fluid Dynamics;
- Mathematical Models;
- Fluid Mechanics and Heat Transfer