Nuclear fuel rod response during LOFT tests L2-2 and L2-3. [PWR]
Conference
·
OSTI ID:5917252
Comparisons of the measured fuel rod peak cladding temperatures for the first two nuclear loss-of-coolant experiments (LOCE), LOCEs L2-2 and L2-3, are presented. These LOCEs were performed in the Loss-of-Fluid Test (LOFT) facility at the Idaho National Engineering Laboratory. The LOCEs provided a basis for evaluating the effect of initial power on the maximum cladding temperatures during a large break (200%, guillotine) LOCE and identified important core thermal-hydraulic responses that influence the peak cladding temperatures.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 5917252
- Report Number(s):
- CONF-791103-29(Summ)
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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SAFETY
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210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
FUEL CANS
LOFT REACTOR
LOSS OF COOLANT
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SIMULATION
STRESSES
TANK TYPE REACTORS
TEMPERATURE GRADIENTS
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THERMAL STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS