Fuel rod mechanical deformation during the PBF/LOFT lead rod loss-of-coolant experiments

Conference · Tue Jan 01 04:00:00 EST 1980

OSTI ID:5260832

Varacalle, Jr., D. J.; MacDonald, P. E.; Shiozawa, S.; Driskell, W. E.

Results of four PBF/LOFT Lead Rod (LLR) sequential blowdown tests conducted in the Power Burst Facility (PBF) are presented. Each test employed four separately shrouded fuel rods. 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 when subjected to a series of double ended cold leg break loss-of-coolant accident (LOCA) tests, and to determine whether subjecting these 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 temperature and system pressure measurements 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: AC07-76ID01570
• OSTI ID: 5260832
• Report Number(s): CONF-800723--18
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
DEFORMATION
FUEL CANS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL RODS
LOFT REACTOR
LOSS OF COOLANT
PRESSURE GRADIENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
STRESSES
TANK TYPE REACTORS
TEMPERATURE GRADIENTS
TEST REACTORS
THERMAL STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS