RADIATION STABILITY OF COMPACTS OF ALUMINUM AND FUEL-BEARING GLASS FIBERS
Technical Report
·
OSTI ID:4761431
Nine clad and unclad composite specimens consisting of glass fibers containing 50 wt% U/sub 3/O/sub 8/ dispersed in a Type 1100 aluminum matrix were irradiated by Battelle at a temperature of 100 deg C to depletion burnups of 17 to 24% % of U/sup 235/ and to fast-neutron (> 1 Mev) exposures of 1 8 x 10/sup 20/ to 2.6 x 10/sup 20/ nvt. The specimens appeared unchanged by the irradiation environment. Swelling as determined by measurements of dimensions and densities was of the same order of magnitude as reported for alloy fuels which experienced similar irradiation exposures. Fission-gas release could be accounted for by the recoil mechanism. The ultimate strengths and elastic moduli were increased and the ductility as determined from elongation measurements did not change appreciably. Metallographic examination did not reveal any evidence of change in the microstructure, and evidence of fission recoil in the matrix was not observed. (auth)
- Research Organization:
- Battelle Memorial Inst., Columbus, Ohio
- DOE Contract Number:
- W-7405-ENG-92
- NSA Number:
- NSA-16-015242
- OSTI ID:
- 4761431
- Report Number(s):
- BMI-1573
- Country of Publication:
- United States
- Language:
- English
Similar Records
FUEL BEARING FIBERGLAS IN ALUMINUM-BASE FUEL ELEMENTS. Final Report
THE EXAMINATION AND EVALUATION OF IRRADIATED THORIUM-11 w/o URANIUM SPECIMENS
EVALUATION OF IRRADIATED ALUMINA-COATED UO$sub 2$ PARTICLES DISPERSED IN GRAPHITE SPHERES
Technical Report
·
Fri Jun 01 00:00:00 EDT 1962
·
OSTI ID:4748113
THE EXAMINATION AND EVALUATION OF IRRADIATED THORIUM-11 w/o URANIUM SPECIMENS
Technical Report
·
Wed Apr 15 23:00:00 EST 1959
·
OSTI ID:4253908
EVALUATION OF IRRADIATED ALUMINA-COATED UO$sub 2$ PARTICLES DISPERSED IN GRAPHITE SPHERES
Technical Report
·
Wed Mar 21 23:00:00 EST 1962
·
OSTI ID:4796483
Related Subjects
ALUMINUM
BURNUP
DEFORMATION
DENSITY
DISPERSIONS
DUCTILITY
EXPANSION
FAST NEUTRONS
FIBERS
FISSION PRODUCTS
FUELS
GASES
GLASS
IRRADIATION
LATTICES
LEAKS
MATERIALS TESTING
MEASURED VALUES
METALLOGRAPHY
METALS, CERAMICS, AND OTHER MATERIALS
NEUTRON BEAMS
RADIATION DOSES
RADIATION EFFECTS
RECOILS
TENSILE PROPERTIES
U3O8
VOLUME
BURNUP
DEFORMATION
DENSITY
DISPERSIONS
DUCTILITY
EXPANSION
FAST NEUTRONS
FIBERS
FISSION PRODUCTS
FUELS
GASES
GLASS
IRRADIATION
LATTICES
LEAKS
MATERIALS TESTING
MEASURED VALUES
METALLOGRAPHY
METALS, CERAMICS, AND OTHER MATERIALS
NEUTRON BEAMS
RADIATION DOSES
RADIATION EFFECTS
RECOILS
TENSILE PROPERTIES
U3O8
VOLUME