PWR FLECHT final report supplement

Technical Report · Sun Oct 01 04:00:00 EDT 1972

OSTI ID:4373001

Cadek, F F; Dominicis, D P; Yeh, H C; Leyse, R H

For Westinghouse Electric Corp., Pittsburgh, Pa. A series of sixteen bottom flooding tests were performed with the PWR-FLECHT test facility to extend the range of FLECHT data to various combinations of low system pressure (15-20 psia), low flooding rate (as low as 0.4 in/sec) and low subcooling (~ 20 deg F). Also, the effect of peak power and test section flow housing temperature were investigated at these conditions. The test results include transient heat transfer coefficients and clad temperatures at different axial and radial locations. Axial pressure drop, local coolant temperature and liquid carryover were also measured. It was found that heat transfer coefficients increased with flooding rate and system pressure. lt was also observed that lower system pressure increased the measured liquid carryover and lowered the velocity of the quench front. Low subcooling was found to increase the quench time but had no effect on heat transfer coefficient until late in the runs. Lowering the peak power increased the heat transfer coefficient for times greater than 120 seconds after flood. The heat transfer coefficient correlation presented in WCAP-7665 was modified to more accurately predict the data at the conditions of the current tests. (auth)

• Research Organization: Aerojet Nuclear Co., Idaho Falls, Idaho (USA)
• NSA Number: NSA-29-007103
• OSTI ID: 4373001
• Report Number(s): WCAP--7931
• Country of Publication: United States
• Language: English

Related Subjects

*CORE FLOODING SYSTEMS-- HEAT TRANSFER
*ECCS-- CORE FLOODING SYSTEMS
*PWR TYPE REACTORS-- ECCS
FLOW RATE
FUEL CANS
N77200 --Reactors--Power Reactors
Non-breeding
Light-water Moderated
Non-boiling Water-cooled
N77900* --Reactors--Reactor Safety & Environmental Aspects
PRESSURE DEPENDENCE
PRESSURE GRADIENTS
TEMPERATURE DEPENDENCE
TESTING
TRANSIENTS PRESSURE GRADIENTS