RADIOCHEMICAL DETERMINATION OF RUTHENIUM BY SOLVENT EXTRACTION AND PREPARATION OF CARRIER-FREE RUTHENIUM ACTIVITY

Journal Article · Mon Jan 01 00:00:00 EST 1962 · Analytical Chemistry (U.S.) Formerly Ind. Eng. Chem., Anal. Ed.

DOI:https://doi.org/10.1021/ac60181a025· OSTI ID:4822547

Meadows, J W.T.; Matlack, G M

Essentially quantitative extractiion of ruthenium tetroxide by carbon tetrachloride from aqueous solutions at pH 4 iorms the basis for a method for determining fission product ruthenium in neutron-irradiated plutonium. In the presence of zirconium holdback carrier, ruthenium is freed from all other fission products by a single extraction. The ruthenium is then back-extracted into dilute sodium hydroxide, precipitated as mixed oxides, mounted in a suitable manner. and beta or gamma counted. The extraction method is as precise as and more rapid than the conventional distillation method. This procedure may also be used for the preparation of carrier-free ruthenium activity. (auth)

• Research Organization: Los Alamos Scientific Lab., N. Mex.
• NSA Number: NSA-16-005275
• OSTI ID: 4822547
• Journal Information: Analytical Chemistry (U.S.) Formerly Ind. Eng. Chem., Anal. Ed., Vol. Vol: 34; Other Information: Orig. Receipt Date: 31-DEC-62
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

CHEMISTRY
ACIDITY
ACTIVATION
ADSORPTION
BETA PARTICLES
CARBON TETRACHLORIDE
COUNTERS
DISTILLATION
FISSION PRODUCTS
GAMMA RADIATION
IRRADIATION
MIXING
NEUTRON SOURCES
OXIDES
PLUTONIUM
PRECIPITATION
PREPARATION
QUANTITATIVE ANALYSIS
RADIOCHEMISTRY
RUTHENIUM
RUTHENIUM OXIDES
SEPARATION PROCESSES
SODIUM HYDROXIDES
SOLUTIONS
SOLVENT EXTRACTION
TRACER TECHNIQUES
WATER
ZIRCONIUM