Fuel-clad interaction. C-E thermo-structural fuel evaluation methods. [PWR; zircaloy; UO/sub 2/]

Technical Report · Thu Apr 01 04:00:00 EST 1976

OSTI ID:7348306

Thermal and irradiation induced distortions experienced during the service life of a fuel rod lead to pellet-clad gap closure and local clad stresses and strains. In addition, presence of fission products can be detrimental to the ability of the clad to sustain such stresses and strains. A thermo-structural fuel evaluation model is described which has been developed to analyze the response of Zircaloy clad uranium dioxide fuel rods during pellet-clad interaction (PCI). The approach taken has been to utilize several analyses consisting of (1) an axisymmetric, cylindrical, pellet average model of history dependent behavior of the fuel rod and (2) pellet distortion and cracking models. Stresses and strains are to be compared with failure criteria to define conditions for which incipient fuel rod failure would exist. A description of the mathematical and behavioral models, failure criteria, and results for typical fuel rod geometries and power histories is presented.

• Research Organization: Combustion Engineering, Inc., Windsor, Conn. (USA)
• OSTI ID: 7348306
• Report Number(s): CENPD-179
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ACTINIDE COMPOUNDS
ALLOYS
CHALCOGENIDES
CRACKS
FUEL CANS
FUEL PELLETS
FUEL-CLADDING INTERACTIONS
MATHEMATICAL MODELS
OXIDES
OXYGEN COMPOUNDS
PELLETS
PWR TYPE REACTORS
REACTORS
STRAINS
STRESSES
TIN ALLOYS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS