Potentiometric determination of free acidity in uranium(VI) and plutonium(IV) solutions and a sequential determination of uranium

Journal Article · Tue Oct 01 00:00:00 EDT 1985 · Anal. Chem.; (United States)

DOI:https://doi.org/10.1021/ac00289a043· OSTI ID:5055816

Ahmed, M K; Suryanarayana, D S; Sabharwal, K N; Sreenivasan, N L

Free acidity in uranium(VI) and plutonium(IV) solutions has been determined with sodium sulfate as complexant and sodium carbonate as titrant. The described method is simple, accurate, and applicable to all ranges of nitric acid and heavy metal concentrations relevant to Purex process. The method is adaptable for remote operation. The overall recovery of nitric acid is 99.5% with 0.7% relative standard deviation. Uranium content has also been determined in the same aliquot with a recovery of 98.5% and 1.2% relative standard deviation after the determination of acidity.

• Research Organization: Reactor Research Center, Kalpakkam, India
• OSTI ID: 5055816
• Journal Information: Anal. Chem.; (United States), Vol. 57:12
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
37 INORGANIC
ORGANIC
PHYSICAL AND ANALYTICAL CHEMISTRY
PLUTONIUM COMPLEXES
PH VALUE
URANIUM
POTENTIOMETRY
URANIUM COMPLEXES
AQUEOUS SOLUTIONS
EXPERIMENTAL DATA
HYDROGEN PEROXIDE
NITRIC ACID
PUREX PROCESS
QUANTITATIVE CHEMICAL ANALYSIS
SODIUM CARBONATES
SODIUM SULFATES
ACTINIDE COMPLEXES
ACTINIDES
ALKALI METAL COMPOUNDS
CARBON COMPOUNDS
CARBONATES
CHEMICAL ANALYSIS
COMPLEXES
DATA
DISPERSIONS
ELEMENTS
HYDROGEN COMPOUNDS
INFORMATION
INORGANIC ACIDS
METALS
MIXTURES
NUMERICAL DATA
OXYGEN COMPOUNDS
PEROXIDES
REPROCESSING
SEPARATION PROCESSES
SODIUM COMPOUNDS
SOLUTIONS
SULFATES
SULFUR COMPOUNDS
TITRATION
TRANSURANIUM COMPLEXES
050800* - Nuclear Fuels- Spent Fuels Reprocessing
400102 - Chemical & Spectral Procedures