Observations on the irradiation behavior of a Zircaloy-4 clad rod containing low density ThO/sub 2/--5. 3 wt. percent UO/sub 2/ pellets (LWBR Development Program)

Technical Report · Mon Dec 01 04:00:00 EST 1969

OSTI ID:7010703

McCauley, J E

A rod-type fuel element, containing low density ThO/sub 2/-5.3 wt % UO/sub 2/ fuel pellets and sheathed in Zircaloy-4, was irradiated to a peak depletion of 1.5 x 10/sup 20/ fissions per cubic centimeter of oxide fuel. The element was located in a relatively steep thermal flux gradient during its entire irradiation lifetime. Post-irradiation observations of grain growth and central void formation in this oxide fuel were found to be reasonably consistent with current theoretical treatments of these phenomena. The irradiation history defined for rod 79-76 as a function of specimen axial location and in-reactor test time was supported indirectly by a semiquantitative evaluation of the microstructural changes obtained in the oxide pellets. (NSA 24: 12488)

• Research Organization: Bettis Atomic Power Lab., Pittsburgh, PA (USA)
• DOE Contract Number: AT(11-1)-GEN-14
• OSTI ID: 7010703
• Report Number(s): WAPD-TM-664
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
ACTINIDE COMPOUNDS
ALLOYS
BREEDER REACTORS
CHALCOGENIDES
FUEL ELEMENTS
FUEL PELLETS
FUEL RODS
LWBR TYPE REACTORS
OXIDES
OXYGEN COMPOUNDS
PELLETS
PHYSICAL RADIATION EFFECTS
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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