Counter-current flow limited CHF in thin rectangular channels

Conference · Mon Jan 01 00:00:00 EST 1990

OSTI ID:6120767

Cheng, L Y

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. 17 refs., 7 figs.

• Research Organization: Brookhaven National Lab., Upton, NY (USA)
• Sponsoring Organization: DOE/ER
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 6120767
• Report Number(s): BNL-45355; CONF-910318-10; ON: DE91004755; TRN: 91-002884
• Resource Relation: Conference: 13. ASME-JSME international solar energy conference, Reno, NV (USA), 17-22 Mar 1991
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
42 ENGINEERING
REACTOR CHANNELS
CRITICAL HEAT FLUX
RESEARCH AND TEST REACTORS
FLOW MODELS
FLOW RATE
FLUID FLOW
RECTANGULAR CONFIGURATION
VOID FRACTION
CONFIGURATION
HEAT FLUX
MATHEMATICAL MODELS
REACTOR COMPONENTS
REACTORS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors
220200 - Nuclear Reactor Technology- Components & Accessories
420400 - Engineering- Heat Transfer & Fluid Flow