THE QUANTITATIVE DETERMINATION OF URANIUM AND BERYLLIUM IN FUSED-SALT SYSTEMS

Technical Report · Sun Apr 01 04:00:00 EST 1956

OSTI ID:4303352

Rogers, N E; Prather, W D

A method is described for the quantitative separation and determination of uranium and beryllium in the presence of macro quantities of sodium in a ternary system of fused fluorides. The fluoride ion is volatilized as fluoboric acid during the dissolution of the dried mixedsalts with acids. The separation of uranium from beryllium and sodium is accomplished by the electrolytic deposition of the uranium as a hydrous oxide on a platinum electrode from a hot ammonium acetate solution at a pH of 4.0. The beryllium remains ln the plating solution with the sodium, and is determined as the hydroxide. Both the uranium deposit and the beryllium hydroxide precipitate are ignited and weighed as their respective oxides. Sodium is determined by means of the flame photometer, or it may be calculated as the difference between the combined weights of the uranium and beryllium fluorides and the original sample weight. (auth)

• Research Organization: Mound Lab., Miamisburg, Ohio
• DOE Contract Number: AT(33-1)-GEN-53
• NSA Number: NSA-13-001117
• OSTI ID: 4303352
• Report Number(s): MLM-1070
• Country of Publication: United States
• Language: English

Related Subjects

ACETATES
ACIDITY
ACIDS
AMMONIUM COMPOUNDS
BERYLLIUM
BERYLLIUM FLUORIDES
BERYLLIUM HYDROXIDES
BERYLLIUM OXIDES
BORON FLUORIDES
BORON OXIDES
CHEMICAL REACTIONS
CHEMISTRY
COLOR
COMBUSTION
ELECTRODEPOSITION
ELECTRODES
EMISSION
EQUATIONS
EXCITATION
FLAMES
FLUORIDES
FLUORINE COMPOUNDS
FUSED SALTS
GRAVIMETRY
IONS
LIGHT
MINERAL ACIDS
MIXING
PHOTOMETRY
PLATINUM
PYROLYSIS
QUALITATIVE ANALYSIS
QUANTITATIVE ANALYSIS
SEPARATION PROCESSES
SODIUM FLUORIDES
SOLUTIONS
SPECTROSCOPY
TEMPERATURE
URANIUM
URANIUM FLUORIDES
URANIUM HYDROXIDES
URANIUM OXIDES
VOLATILITY
WEIGHT