A STUDY OF THE RADIATION STABILITY OF UO$sub 2$ DISPERSIONS IN BeO
An experiment was performed to determine the radiation stability of beryllium oxide fueled with approximately 56 wt.% UO/sub 2/. Pellets of BeO-UO/ sub 2/ were prepared by coldpressing techniques followed by sintering at 2800 deg F for 2 hr in a hydrogen atmosphere. These pellets were contained in Hastelloy-X tubes sealed by heliarc welding. Temperature measurements and burn-up analysis by isotopic techniques indicated that the specimen surface temperatures ranged from 1450 to 1725 deg F with burn-ups ranging from 1.5 to 2.0 at.% of the U/sup 235/. A specimen similar to the irradiation specimens was thermally cycled at temperatures simulating, as closely as possible, those experienced by the irradiation specimens. These fueled pellets did not show any changes in their physical properties or microstructures. The postirradiation examination of the specimens from Capsule GCRE-BRR-II included fissiongas analyses, dimensional and density measurements, isotopic burn-up analysis, and detailed metallographic examinations of both the fueled BeO pellets and the Hastelloy-X tubes. Only negligible changes in the physical properties were detected. The visual and metallographic examinations of the fueled BeO pellets did not reveal any structural changes. An irregular ring type configuration was observed on the inner surface of the Hastelloy-X tubes. The metallographic examination of a longitudinal edge of these tubes showed ridges and recessed areas which by measurement corresponded relatively well with the configuration observed on the inner surface. These results indicate that BeO fueled with approximately 56 wt.% UO/sub 2/ dispersions withstood irradiation to 2 at.% burn-up of the U/sup 235/ at temperatures near 1800 deg F without any detrimental effects. (auth)
- Research Organization:
- Battelle Memorial Inst., Columbus, Ohio
- DOE Contract Number:
- W-7405-ENG-92
- NSA Number:
- NSA-15-009502
- OSTI ID:
- 4097681
- Report Number(s):
- BMI-1484
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-61
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
BERYLLIUM OXIDES
BURNUP
CHROMIUM ALLOYS
COLD WORKING
COMPACTING
DEFECTS
DENSITY
DISPERSIONS
DISTRIBUTION
ELECTRIC ARCS
EXPANSION
FABRICATION
FISSION PRODUCTS
FUEL CANS
GASES
HASTELLOY
HEAT TREATMENTS
HEATING
HELIUM
HIGH TEMPERATURE
HYDROGEN
INERT GASES
IRRADIATION
ISOTOPES
MATERIALS TESTING
MEASURED VALUES
METALLOGRAPHY
MOLYBDENUM ALLOYS
NICKEL ALLOYS
PELLETS
RADIATION EFFECTS
SINTERING
SURFACES
TEMPERATURE
THERMAL STRESSES
TUBES
URANIUM DIOXIDE
WELDING