Fuel rod mechanical deformation during the PBF/LOFT lead rod loss-of-coolant experiments
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; TRN: 80-013600
- Resource Relation:
- Conference: 19. national heat transfer conference, Orlando, FL, USA, 27 Jul 1980
- Country of Publication:
- United States
- Language:
- English
Similar Records
Thermal-hydraulics of the PFB/LOFT lead rod loss-of-coolant experiments. [PWR]
An Evaluation of the PBF LOFT Lead Rod Test Results Concerning Surface Thermocouple Perturbation Effects
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FUEL RODS
DEFORMATION
THERMAL STRESSES
LOSS OF COOLANT
PRESSURE GRADIENTS
TEMPERATURE GRADIENTS
PWR TYPE REACTORS
FUEL CANS
FUEL ELEMENT FAILURE
LOFT REACTOR
REACTOR SAFETY
ACCIDENTS
FUEL ELEMENTS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
STRESSES
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors