IRRADIATION OF ZIRCALOY-2 CLAD URANIUM RODS IN NaK-FILLED CAPSULES, GEH 3- 31, 32, 57, 58, AND 59. Final Report

Technical Report · Mon Oct 01 04:00:00 EDT 1962

OSTI ID:4727060

Weber, J W

Physical properties, particularly swelling in the temperature ranges 250- 350 and 450-600 un. Concent 85% C, of Zircaloy-2-clad uranium were studied by irradiating five capsules, each containing a single fuel rod (0.630-inch- diameter) clad with 0.030-inch- Zircaloy-2. Dimensional and density measurements were made along with metallographic observations. Design and fabrication of the elements, irradiation, and the results are discussed. Above 400 un. Concent 85% C, Zircaloy-2 displayed considerable volume increase while significant uranium cracking occurred at 450 un. Concent 85% C and above. Incongruencies were noted in the cladding strains under which the cladding failed. Uranium was observed to have entirely different properties during and after irradiation. Grain structure in uranium also appeared at 450 un. Concent 85% C and changed above 500 un. Concent 85% C. Above 400 un. Concent 85% C both intergranular and transgranular cracking occurred in uranium. Other microstructural features were observed. (D.C.W.)

• Research Organization: General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
• DOE Contract Number: AT(45-1)-1350
• NSA Number: NSA-17-022221
• OSTI ID: 4727060
• Report Number(s): HW-67072
• Country of Publication: United States
• Language: English

Related Subjects

CAPSULES
CRACKS
DEFORMATION
DENSITY
EXPANSION
FABRICATION
FAILURES
FUEL CANS
GRAIN BOUNDARIES
GRAIN SIZE
IRRADIATION
MATERIALS TESTING
METALLOGRAPHY
METALS, CERAMICS, AND OTHER MATERIALS
PLANNING
REPORT
RODS
SODIUM ALLOYS
TEMPERATURE
URANIUM
VARIATIONS
ZIRCALOY