Power-Cooling-Mismatch Test Series Test PCM-1: fuel rod behavior report. [PWR]
The fuel rod behavior results of the Power-Cooling-Mismatch (PCM) Test Series, Test PCM-1 are presented. The objectives of the test were to evaluate the behavior of a pressurized water reactor (PWR) type fuel rod operated at high temperatures in film boiling for a time beyond rod failure with large local regions of molten fuel, and to evaluate the consequences of the continued operation. Test PCM-1, conducted in the Power Burst Facility, employed one 0.914-m-long PWR-design fuel rod, fabricated from unirradiated Zircaloy-4 and pressurized to 2.58 MPa with a fill gas of 77.7% helium and 22.3% argon. The rod was subjected to a preconditioning period and a power ramp to 69 kW/m rod peak power at a constant mass flux of 1110 kg/s.m/sup 2/. The power was subsequently adjusted to 78 kW/m. The rod underwent film boiling during the power ramp to 69 kW/m and failed about 500 seconds later (about 470 seconds of film boiling operation at the peak temperature location). The test rod was in film boiling for 900 seconds with up to 85% of the local fuel pellet radius molten. The test information extends the existing PCM data base to include film boiling operation of a single fuel rod for a significant time beyond failure.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 6021522
- Report Number(s):
- NUREG/CR-0907; TREE-1374
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
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22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BOILING
FILM BOILING
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL RODS
MELTDOWN
PHASE TRANSFORMATIONS
POWER-COOLING-MISMATCH ACCIDENTS
PRESSURE GRADIENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
SIMULATION
TEMPERATURE GRADIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BOILING
FILM BOILING
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL RODS
MELTDOWN
PHASE TRANSFORMATIONS
POWER-COOLING-MISMATCH ACCIDENTS
PRESSURE GRADIENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
SIMULATION
TEMPERATURE GRADIENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS