In-pile dimensional changes of ThO/sub 2/--UO/sub 2/ fuel rods with non-free-standing cladding (LWBR Development Program)

Technical Report · Sun Nov 01 04:00:00 EST 1970

OSTI ID:6742110

Giovengo, J F

Test data obtained from irradiation of bulk oxide Zircaloy clad fuel rods have been evaluated to determine the effect of several geometrical and environmental test variables on the observed post-irradiation dimensional changes. The major variables include clad-heat treatment, fast flux (nv), pellet end configuration, fuel center temperature, clad diameter-to-thickness ratio, accelerated power cycling and pressure cycles. Data indicates clad heat treatment, fast flux environment, pellet end configuration and fuel center temperature have a large effect on rod elongation believed to be caused by an ''axial ratchetting'' mechanism. The other test variables considered show much less of an effect, if any, on the observed dimensional changes resulting from ''axial ratchetting'' of the non-free-standing Zircaloy-4 cladding. 3 references. (NSA 25: 15366)

• Research Organization: Bettis Atomic Power Lab., Pittsburgh, PA (USA)
• DOE Contract Number: AT(11-1)-GEN-14
• OSTI ID: 6742110
• Report Number(s): WAPD-TM-986
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
36 MATERIALS SCIENCE
360106 -- Metals & Alloys-- Radiation Effects
360206 -- Ceramics
Cermets
& Refractories-- Radiation Effects
ACTINIDE COMPOUNDS
ALLOYS
BREEDER REACTORS
CHALCOGENIDES
DEFORMATION
FUEL ELEMENTS
FUEL RODS
LWBR TYPE REACTORS
OXIDES
OXYGEN COMPOUNDS
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
RATCHETING
REACTOR COMPONENTS
REACTORS
THERMAL REACTORS
THORIUM COMPOUNDS
THORIUM OXIDES
TIN ALLOYS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCALOY 4
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS