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Results of the PBF/LOFT Lead Rod Test Series

Conference ·
OSTI ID:5847247
; ;
The PBF/LOFT Lead Rod (PBF/LLR) Test Series consisted of four sequential, nuclear blowdown experiments (Test LLR-3, LLR-5, LLR-4, and LLR-4A). The primary objective of the test series was to evaluate the extent of mechanical deformation that would be expected to occur to low pressure (0.1 MPa) light water reactor design fuel rods subjected to a series of nuclear blowdown tests, and to determine if subjecting deformed fuel rods to subsequent testing would result in rod failure. The extent of mechanical deformation (buckling, collapse, or waisting of the cladding) was evaluated by comparison of cladding temperatue versus system pressure response with out-of-pile experimental data and by posttest visual examinations and cladding diametral measurements.
Research Organization:
EG and G Idaho, Inc., Idaho Falls (USA)
Sponsoring Organization:
USDOE
DOE Contract Number:
EY-76-C-07-1570
OSTI ID:
5847247
Report Number(s):
CONF-7906144-1
Country of Publication:
United States
Language:
English

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDE COMPOUNDS
ALLOYS
BLOWDOWN
CHALCOGENIDES
DEFORMATION
ENERGY TRANSFER
FLUID MECHANICS
FUEL CANS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL RODS
HEAT TRANSFER
HYDRAULICS
LOFT REACTOR
LOSS OF COOLANT
MECHANICS
OXIDES
OXYGEN COMPOUNDS
PERFORMANCE TESTING
PRESSURE GRADIENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SIMULATION
STRESSES
TANK TYPE REACTORS
TEMPERATURE GRADIENTS
TEST REACTORS
TESTING
THERMAL STRESSES
TIN ALLOYS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCALOY 4
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS