PWR FLECHT SEASET unblocked bundle, forced and gravity reflood task data report. Volume 1
This report presents data from the Unblocked Bundle, Forced and Gravity Reflood Task of the Full-Length Emergency Core Heat Transfer Separate Effects and Systems Effects Tests (FLECHT SEASET) program. The tests consisted of forced and gravity reflood experiments and steam cooling tests, using electrical heater rods to simulate current nuclear fuel arrays (similar to Westinghouse 17 x 17 assemblies) of PWR and PWR fuel vendors. Data obtained include rod clad temperatures, turnaround and quench times, heat transfer coefficients, inlet flooding rates, overall mass balance, differential pressures and calculated void fractions in the test section, thimble wall and steam temperatures, and exhaust steam and liquid carryover rates.
- Research Organization:
- Westinghouse Electric Corp., Pittsburgh, PA (USA). Nuclear Energy Systems Div.
- OSTI ID:
- 5697775
- Report Number(s):
- EPRI-NP-1459-Vol.1; NUREG/CR-1532-Vol.1; WCAP-9699-Vol.1; ON: TI85920698
- Country of Publication:
- United States
- Language:
- English
Similar Records
PWR FLECHT-SEASET unblocked bundle, forced and gravity reflood task: task plan report
PWR FLECHT SEASET 161-rod bundle flow blockage task, task plan report
Related Subjects
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
DATA
ENERGY TRANSFER
EXPERIMENTAL DATA
FLUID MECHANICS
FUEL ASSEMBLIES
FUEL ELEMENTS
FUEL RODS
HEAT TRANSFER
HYDRAULICS
INFORMATION
LOSS OF COOLANT
MECHANICS
NUMERICAL DATA
PRESSURE GRADIENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
TEMPERATURE GRADIENTS
TEST FACILITIES
WATER COOLED REACTORS
WATER MODERATED REACTORS