Variations in Zircaloy-4 cladding deformation in replicate LOCA simulation tests. [PWR]
Five single-rod, heated-shroud replicate burst tests were conducted to study statistical variations in Zircaloy cladding deformation under simulated loss-of-coolant accident conditions. The test conditions used (low steam coolant flow and a heating rate of approx. 10 K/s to tube failure at approx. 775/sup 0/C) were conductive to large deformation and matched those used in two of the Multirod Burst Test Program bundle tests so that the results could be used to aid in interpretation of differences observed for individual rods in bundle tests. The largest variation observed was in burst strain, which ranged from 50 to 96%. Burst temperature ranged from 767 to 779/sup 0/C, burst pressure from 9405 to 9870 kPa, average strain over the heated length from 18 to 23%, and tube volume increase from 39 to 51%. As expected, cladding deformation was influenced by small temperature gradients: the more uniform the temperature, the greater (and more uniform) the deformation.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 6673111
- Report Number(s):
- NUREG/CR-2810; ORNL/TM-8413; ON: DE83000433
- Country of Publication:
- United States
- Language:
- English
Similar Records
Effect of bundle size on cladding deformation in LOCA simulation tests
Experiment data report for Multirod Burst Test (MRBT) Bundle B-5. [PWR]
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FUEL CANS
THERMAL STRESSES
FUEL ELEMENT FAILURE
TEST FACILITIES
LOSS OF COOLANT
PWR TYPE REACTORS
FUEL RODS
REACTOR SAFETY
STRAINS
TEMPERATURE DISTRIBUTION
ZIRCALOY 4
ACCIDENTS
ALLOYS
FUEL ELEMENTS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
STRESSES
TIN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled