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

Author
Rogers, N. E.
Published
United States : [publisher not identified], 1956.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1956.
Physical Description
microopaque : positive ; 8 x 13 cm
Additional Creators
Prather, W. D.

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Summary
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)
Report Numbers
MLM-1070
Other Subject(s)
Collection
U.S. Atomic Energy Commission depository collection.
Note
DOE contract number: AT-33-1-GEN-53
NSA number: NSA-13-001117
OSTI Identifier 4303352
Research organization: Mound Lab., Miamisburg, Ohio.
View MARC record | catkey: 41322376