Power-Cooling-Mismatch Test Series: Test PCM-3 postirradiation examination. [PWR]
The results are presented of the postirradiation examination of four previously unirradiated pressurized water reactor (PWR) type fuel rods tested in-pile in pre- and post-DNB (departure from nucleate boiling) operation. All four rods remained intact during the DNB testing and subsequent reactor shutdown. Two of the tested fuel rods showed evidence of surface damage, characterized by cladding collapse and oxide spalling. Metallographic examination of the cladding microstructure of the two fuel rods which exhibited extensive collapse in the film boiling zone indicated that those rods operated at temperatures above the ..cap alpha.. + ..beta.. to ..beta..-phase transformation temperature of 1245/sup 0/K for the zircaloy cladding. The other two fuel rods, which exhibited less extensive collapse, operated at temperatures below the ..cap alpha.. + ..beta.. phase transformation temperature of 1105/sup 0/K. Rod A-0021 failed during remote handling following the test. Prior beta grain boundary embrittlement is postulated as the failure mechanism.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 5287158
- Report Number(s):
- TREE-NUREG-1187
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDE COMPOUNDS
ALLOYS
BOILING
CHALCOGENIDES
DEPARTURE NUCLEATE BOILING
FUEL ELEMENTS
FUEL RODS
NUCLEATE BOILING
OXIDES
OXYGEN COMPOUNDS
PERFORMANCE TESTING
PHASE TRANSFORMATIONS
POWER-COOLING-MISMATCH ACCIDENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
TESTING
TIN ALLOYS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCALOY 4
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS