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Power-Cooling Mismatch Test series. Test PCM-1, Quick Look Report

Technical Report ·
OSTI ID:6495509
;
The Power-Cooling-Mismatch (PCM) Test, PCM-1 was conducted on March 30, 1978 in the Power Burst Facility at the Idaho National Engineering Laboratory. The test was the eighth test in the series of PCM tests designed to characterize the behavior of nuclear fuel rods operating under various combinations of lower than normal coolant flow and higher than normal rod power. The PCM-1 test consisted of a single PWR designed fuel rod containing a 0.91 m long stack of unirradiated UO/sub 2/ fuel pellets. The objective of the test was to simulate a severe PCM incident leading to fuel rod failure at power with sufficient molten fuel present within the rod to produce a high probability of molten fuel-coolant interaction (MFCI) when failure occurred. 14 figs.
Research Organization:
EG and G Idaho, Inc., Idaho Falls (USA)
DOE Contract Number:
AC07-76ID01570
OSTI ID:
6495509
Report Number(s):
TFBP-TR-262; ON: TI85016659
Country of Publication:
United States
Language:
English

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDE COMPOUNDS
CHALCOGENIDES
COOLING SYSTEMS
CRACKS
CRITICAL HEAT FLUX
ENERGY SYSTEMS
FAILURES
FLUID FLOW
FLUID MECHANICS
FUEL ELEMENTS
FUEL RODS
FUEL-CLADDING INTERACTIONS
FUEL-COOLANT INTERACTIONS
HEAT FLUX
HIGH TEMPERATURE
HYDRAULICS
MEASURING INSTRUMENTS
MECHANICS
MELTDOWN
NEUTRON DETECTORS
NEUTRON FLUX
OXIDES
OXYGEN COMPOUNDS
PBF REACTOR
POWER-COOLING-MISMATCH ACCIDENTS
PULSED REACTORS
PWR TYPE REACTORS
RADIATION DETECTORS
RADIATION FLUX
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
TANK TYPE REACTORS
TESTING
THERMODYNAMICS
URANIUM COMPOUNDS
URANIUM OXIDES
VERY HIGH TEMPERATURE
WATER COOLED REACTORS
WATER MODERATED REACTORS