Temperature estimates from zircaloy oxidation kinetics and microstructures. [PWR]

Technical Report · Fri Oct 01 04:00:00 EDT 1982

OSTI ID:6673121

Olsen, C S

This report reviews state-of-the-art capability to determine peak zircaloy fuel rod cladding temperatures following an abnormal temperature excursion in a nuclear reactor, based on postirradiation metallographic analysis of zircaloy microstructural and oxidation characteristics. Results of a comprehensive literature search are presented to evaluate the suitability of available zircaloy microstructural and oxidation data for estimating anticipated reactor fuel rod cladding temperatures. Additional oxidation experiments were conducted to evaluate low-temperature zircaloy oxidation characteristics for postirradiation estimation of cladding temperature by metallographic examination. Results of these experiments were used to calculate peak cladding temperatures of electrical heater rods and nuclear fuel rods that had been subjected to reactor temperature transients. Comparison of the calculated and measured peak cladding temperatures for these rods indicates that oxidation kinetics is a viable technique for estimating peak cladding temperatures over a broad temperature range. However, further improvement in zircaloy microstructure technology is necessary for precise estimation of peak cladding temperatures by microstructural examination.

• Research Organization: Idaho National Engineering Lab., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 6673121
• Report Number(s): NUREG/CR-2807; EGG-2207; ON: DE83002626
• Country of Publication: United States
• Language: English

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ACCIDENTS
ALLOYS
CHEMICAL REACTIONS
CRYSTAL STRUCTURE
ECCS
ENGINEERED SAFETY SYSTEMS
FUEL CANS
FUEL ELEMENTS
FUEL RODS
LOFT REACTOR
LOSS OF COOLANT
MICROSTRUCTURE
MONITORING
OXIDATION
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
STRESSES
TANK TYPE REACTORS
TEMPERATURE DEPENDENCE
TEMPERATURE DISTRIBUTION
TEMPERATURE MONITORING
TEST REACTORS
THERMAL STRESSES
TIN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS