THE USE OF PLUTONIUM AS FUEL IN NUCLEAR REACTORS. Quarterly Report No. 5, July 1-September 30, 1961
- Published
- United States : [publisher not identified], 1961.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1961. - Physical Description
- microfiche : negative ; 8 x 13 cm
- Summary
- Plutonium dioxide, prepared from precipitated oxalate, dissolves easily in a nitric acid-hydrofluoric acid mixture. The effects of iron on the fluorometric analysis of uranium was determined. As regards the potentiometric analysis of plutonium, the choice of indicator electrode, the effects of catalysers, and the reagent addition rate were examined. Plutonium carbide was produced from plutonium dioxide and graphite. By uranium dioxide vibration, densities around 89% of the theoretical density were obtained. By cold swaging densities around 94% of the theoretical density of uranium dioxide and 9l% of the density of uranium carbide were obtained. The zirconium alloy powders produced have a lower hydrogen content than powders obtained commercially. Zirconium and Zircaloy-2 dispersions were fabricated. Dilatometric results were obtained on stoichiometric and substoichiometric plutonium dioxide and plutonium dioxide- uranium dioxide mixtures. The phases of the niobium-zirconium alloys were established. Different chemical baths for polishing niobium-zirconium alloys were tried for their preparation with a view to corrosion tests. Tensile tests on niobium-zirconium alloys were made along with creep tests. A heat conductivity measurement instrument was developed. (auth)
- Report Numbers
- EURAEC-176; BN-6110-01
- Other Subject(s)
- Catalysis
- Cleaning
- Cold working
- Corrosion
- Creep
- Density
- Electric potential
- Electrodes
- Expansion
- Fuels
- Graphite
- Hydrofluoric acid
- Hydrogen
- Iron
- Laboratory equipment
- Machining
- Materials testing
- Measured values
- Metals, ceramics, and other materials
- Niobium alloys
- Nitric acid
- Oxalates
- Phase diagrams
- Plutonium carbides
- Plutonium oxides
- Plutonium
- Powders
- Precipitation
- Production
- Qualitative analysis
- Quantitative analysis
- Quantity ratio
- Reactors
- Solutions
- Tensile properties
- Thermal conductivity
- Uranium carbides
- Uranium dioxide
- Uranium
- Uses
- Vibrations
- Zircaloy
- Zirconium alloys
- Zirconium
- Collection
- U.S. Atomic Energy Commission depository collection.
- Note
- DOE contract number: 027-60-7-RDB
NSA number: NSA-18-002158
OSTI Identifier 4144590
Research organization: Societe Belge pour l'Industrie Nucleaire, Brussels and Brussels. Centre d'Etude de l'Energie Nucleaire.
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