PBF LOCA test LOC-6 fuel-behavior report. [PWR]
Technical Report
·
OSTI ID:6137957
This report presents the results of Loss-of-Coolant (LOC) Test LOC-6, conducted in the Power Burst Facility at the Idaho National Engineering Laboratory by EG and G Idaho, Inc., for the US Nuclear Regulatory Commission. Postirradiation examination results are included, together with the results of thermal-hydraulic and fuel behavior calculations using the RELAP4 and FRAP-T6/BALON-2 computer codes. Two of the four light water reactor type fuel rods ballooned and ruptured during the test. Peak cladding temperatures at the rupture locations were high in the alpha phase (1066 and 1098/sup 0/K). The effects of initial rod internal prepressurization and prior irradiation were investigated during the experiment. The effect of rod prepressurization was found to be significant, and, for burnups of about 17,000 MWd/t, prior irradiation increased cladding circumferential strains at failure.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 6137957
- Report Number(s):
- NUREG/CR-3184; EGG-2244; ON: DE83012115
- Country of Publication:
- United States
- Language:
- English
Similar Records
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Conference
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·
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·
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·
OSTI ID:6702938
Related Subjects
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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
COMPUTER CALCULATIONS
ENERGY TRANSFER
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FUEL ELEMENTS
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HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
PRESSURE GRADIENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
SAFETY
STRAINS
STRESSES
TEMPERATURE GRADIENTS
TEST FACILITIES
THERMAL STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS