SUMMARY TECHNICAL REPORT FOR THE PERIOD JULY 1, 1957 TO SEPTEMBER 30, 1957
Technical Report
·
OSTI ID:4843019
The processing of thorium-bearing uranium concentrates by phosphate complexing was demonstrated and placed on a regular production basis. The effects of acid concentration and chloride concentration on the oxidation of chloride in an electrolytic fiow cell were evaluated. A method for treating used solvent from the refinery was developed. Results indicated that cation carryover can be reduced by using a modified solvent treatment system. Reactivity of orange oxide was increased by adding ammonia to the uranyl nitrate product, but not to the degree realized with suifate addition. The oxidative characteristics of UO/sub 2/ and their relationship to the hydrofluorination characteristics were studied. The presence of lithium in orange oxide was observed to be more detrimental to subsequent hydrofluorination than either sodium or potassium. Rate data for the hydrofluorination reaction were obtained for two types of feed material with the gas phase containing vanious concentrations of HF and H/sub 2/O. The regeneration of waste KF solution for reuse in the KOH neutralization of HF off-gases was studied. Heat transfer data obtained during dehydration of UO/sub 3/ pellets in the moving bed reactor were evaluated and correlated. Studies showed the feasibility of using H/sub 2/SO/sub 4/ as a substitute for HCl for leaching uranium from hydrometallurgical system scrap feed. Equipment is being developed for producing uranium metal by the continuous reduction of uranium tetrafluoride with magnesium. Melts were cast from charges that consisted of one or two components of the usual remelt charge. Data were obtained on the effect of each component on the carbon and nitrogen levels in ingots and the percentage yield of good slugs. A satisfactory polarographic method was developed for the determination of iron in uranyl nitrate and uranium tetrafluoride. A spectrographic method which uses a mixed carrier material in the analysis of U/ sub 3/O/sub 8/ improved the excitation of iron and nickel, resulting in improved analytical precisions for these two elements. (auth)
- Research Organization:
- National Lead Co. of Ohio, Cincinnati
- NSA Number:
- NSA-15-029271
- OSTI ID:
- 4843019
- Report Number(s):
- NLCO-690(Del.)
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
ACIDS
AMMONIA
CARBON
CASTING
CATIONS
CHEMISTRY
CHLORIDES
COMPLEXES
ELECTROLYSIS
ELECTROLYTIC CELLS
FLUORINATION
GASES
HEAT TRANSFER
HYDROCHLORIC ACID
HYDROGEN FLUORIDES
IRON
LEACHING
LITHIUM
MEASURED VALUES
MELTING
METALLURGY
METALS
NICKEL
NITROGEN
ORE PROCESSING
OXIDATION
PELLETS
PHOSPHATES
POLAROGRAPHY
POTASSIUM
POTASSIUM FLUORIDES
POTASSIUM HYDROXIDES
PRODUCTION
QUANTITATIVE ANALYSIS
SODIUM
SOLVENTS
SPECTRA
SULFATES
SULFURIC ACID
THORIUM
URANIUM
URANIUM CONCENTRATES
URANIUM DIOXIDE
URANIUM ORES
URANIUM OXIDES
URANIUM TETRAFLUORIDE
URANIUM TRIOXIDE
URANYL NITRATES
WASTE PROCESSING
AMMONIA
CARBON
CASTING
CATIONS
CHEMISTRY
CHLORIDES
COMPLEXES
ELECTROLYSIS
ELECTROLYTIC CELLS
FLUORINATION
GASES
HEAT TRANSFER
HYDROCHLORIC ACID
HYDROGEN FLUORIDES
IRON
LEACHING
LITHIUM
MEASURED VALUES
MELTING
METALLURGY
METALS
NICKEL
NITROGEN
ORE PROCESSING
OXIDATION
PELLETS
PHOSPHATES
POLAROGRAPHY
POTASSIUM
POTASSIUM FLUORIDES
POTASSIUM HYDROXIDES
PRODUCTION
QUANTITATIVE ANALYSIS
SODIUM
SOLVENTS
SPECTRA
SULFATES
SULFURIC ACID
THORIUM
URANIUM
URANIUM CONCENTRATES
URANIUM DIOXIDE
URANIUM ORES
URANIUM OXIDES
URANIUM TETRAFLUORIDE
URANIUM TRIOXIDE
URANYL NITRATES
WASTE PROCESSING