ANNUAL PROGRESS REPORT ON FUEL ELEMENT DEVELOPMENT FOR FISCAL YEAR 1961

Technical Report · Thu Mar 01 00:00:00 EST 1962

DOI:https://doi.org/10.2172/4782699· OSTI ID:4782699

Gibson, G W; Shupe, O K

Progress in fuels and materials development is summarized. Major areas of investigation include a materials study by means of sample fuel plates containing uranium alloys or cermets, burnable poisons, non-uniform fuel and poison distributions and clad with various aluminum alloys; and an engineering study of fuel element geometries optimized in heat transfer, hydraulics, and materials strength. Up to 45 wt% U-Al alloys, 6 to 65 wt% UO/-Al and U3O6-Al dispersions, including enrichments ranging from 20% to 93%, were tested to 70% burnup in de-ionized water at 200 deg F in the MTR. Their performance at higher temperature is still being investigated. Test results for the MTR conditions indicate that all of the compositions investigated to date will successfully withstand even the longest irradiation at these conditions if properly fabricated. Some high strength aluminum alloy claddings, not yet fully tested, show some peculiar surface effects which may be related to corrosion. Metallographic studies of irradiated cermets reveal a reaction'' (diffusion) zone produced around UO/sub 2/ particles in contact with aluminum. These zones are being studied by means of x-ray diffraction, electron microscopy, and electron microprobe analysis. From engineering studies has come promise of improved heat removal and lower pumping requlrements for reactors through artificial roughening of fuel plates. Computer optimizatlon studies and hydraulic tests indicated 80% improvement in heat transfer or 60% less flow for the same heat load are obtainable for MTR conditions. Heat transfer test results from 0.110 x 2.624 ' electrically-heated channels using heat fluxes up to 2.88 x 10/sup 6/ Btu/hr-ft/ sup 2/, sgree better with correlations based on bulk temperatures than with the more widely used modified Colburn equation. In this range, a modifled Colburn equation with a 20% safety factor, as is presently used, seems adequate. However, an equation based on the bulk coolant temperature could be used employing a smaller safety factor because of its greater accuracy. ( auth)

• Research Organization: Phillips Petroleum Co. Atomic Energy Div., Idaho Falls, Idaho
• Sponsoring Organization: USDOE
• DOE Contract Number: AT(10-1)-205
• NSA Number: NSA-16-015905
• OSTI ID: 4782699
• Report Number(s): IDO-16727
• Resource Relation: Other Information: Orig. Receipt Date: 31-DEC-62
• Country of Publication: United States
• Language: English

Related Subjects

REACTOR TECHNOLOGY
ALUMINUM ALLOYS
BURNOUT
BURNUP
CANNING
CERMETS
COLBURN EQUATION
COMPUTERS
CONFIGURATION
COOLANT LOOPS
CORROSION
DIFFUSION
DISPERSIONS
DISTRIBUTION
ELECTRON MICROSCOPY
ENRICHMENT
EQUATIONS
FABRICATION
FLUID FLOW
FUEL CANS
FUEL ELEMENTS
FUELS
HEAT TRANSFER
HIGH TEMPERATURE
HYDRAULICS
INSPECTION
IRRADIATION
METALLOGRAPHY
MTR
PERFORMANCE
PLATES
POISONING
SURFACES
TESTING
URANIUM ALLOYS
URANIUM DIOXIDE
URANIUM OXIDES
VARIATIONS
WATER COOLANT
X RADIATION
ZONES