HIGH-TEMPERATURE IRRADIATION OF UO$sub 2$-BeO BODIES
As a part of the ML-1 reactor fuel evaluation program, UO/sub 2/-- BeO bodies containing two UO/sub 2/ compositions, 70 and 80 wt% UO/sub 2/, were irradiated to a burnup equivalent to 8750 hours of ML-1 reactor operation (8.5% U/ sup 235/). It was estimated that maximum cladding surface temperatures of 1710 nif- F were attained during irradiation. Reference design burnup for the ML-1 is 9.7% U/sup 235/, in 10,000 hours of operation at maximum clad surface temperatures of 1750 nif- F. Postirradiation examination of the test specimens revealed that the cladding of one of the 80 wt% UO/sub 2/-- BeO specimens had ruptured after severe swelling. All other specimens showed little external effect from the irradiation. Fission gas release from the fuel varied between 0.59 and 2.7% except for the failed specimen which released about 69%. Considerable change was observed in the microstructure of the irradiated specimens although subsequent x-ray diffraction examination did not indicate serious damage to the crystal structure of either the BeO or UO/sub 2/. The data obtained from this experiment are in substantial agreement with that determined in irradiation experiments performed at other facilities. The performance of 70 wt% UO/sub 2/--BeO was considered to be suitable for use in the ML-1 reactor. (auth)
- Research Organization:
- Aerojet-General Nucleonics, San Ramon, Calif.; Battelle Memorial Inst., Columbus, Ohio
- Sponsoring Organization:
- USDOE
- NSA Number:
- NSA-17-018856
- OSTI ID:
- 4739395
- Report Number(s):
- IDO-28600
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
BERYLLIUM OXIDES
BURNUP
COATING
CONFIGURATION
CRYSTALS
DIFFRACTION
EXPANSION
FAILURES
FISSION PRODUCTS
FUEL ELEMENTS
GASES
HIGH TEMPERATURE
IRRADIATION
MATERIALS TESTING
METALLOGRAPHY
METALS, CERAMICS, AND OTHER MATERIALS
ML-1
RADIATION EFFECTS
REACTORS
SURFACES
URANIUM 235
URANIUM DIOXIDE
X RADIATION
BURNUP
COATING
CONFIGURATION
CRYSTALS
DIFFRACTION
EXPANSION
FAILURES
FISSION PRODUCTS
FUEL ELEMENTS
GASES
HIGH TEMPERATURE
IRRADIATION
MATERIALS TESTING
METALLOGRAPHY
METALS, CERAMICS, AND OTHER MATERIALS
ML-1
RADIATION EFFECTS
REACTORS
SURFACES
URANIUM 235
URANIUM DIOXIDE
X RADIATION