Analysis of void migration, clad collapse and fuel cracking in bulk oxide fuel rods (LWBR Development Program)

Technical Report · Mon Jul 01 04:00:00 EDT 1968

OSTI ID:6747346

Duncombe, E

Methods of accounting for void migration, fuel cracking, fuel-clad friction and clad collapse in the analysis of the performance of bulk oxide fuel rods are presented. The required modifications to the CYGRO-2 computer program are specified. The observed coring radius of a fuel rod containing ThO/sub 2/ 5.6 w/o UO/sub 2/ is in agreement with the model if suitable allowance is made for fission-induced swelling. In-pile length changes of a non-free-standing test fuel rod containing ThO/sub 2/ 20 w/o UO/sub 2/ are also explained on the basis of the fuel cracking model. (NSA 22: 47047)

• Research Organization: Bettis Atomic Power Lab., Pittsburgh, PA (USA)
• DOE Contract Number: AT(11-1)-GEN-14
• OSTI ID: 6747346
• Report Number(s): WAPD-TM-794
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
ACCIDENTS
ACTINIDE COMPOUNDS
BREEDER REACTORS
CHALCOGENIDES
CRACKS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL PELLETS
FUEL RODS
FUEL-CLADDING INTERACTIONS
LWBR TYPE REACTORS
OXIDES
OXYGEN COMPOUNDS
PELLETS
PERFORMANCE
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
THERMAL REACTORS
THORIUM COMPOUNDS
THORIUM OXIDES
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
VOIDS
WATER COOLED REACTORS
WATER MODERATED REACTORS