Improved mathematical models of actinide extraction by 30% solutions of the tri-n-butylphosphate in diluents

Journal Article · Thu Oct 01 04:00:00 EDT 1987 · Sov. At. Energy (Engl. Transl.); (United States)

DOI:https://doi.org/10.1007/BF01123365· OSTI ID:5863806

Rozen, A M; Andrutskii, L G; Vlasov, V S

The authors construct mathematical models describing the solvent extraction of uranium, neptunium, and plutonium ions with tri-n-butylphosphate in aqueous solutions also containing diluents such as nitric acid, dodecane, kerosene, and synthene. They analyze the sensitivity of their models to changing parameters such as solvent concentration and valence against established experimental data for the process for these actinides.

• OSTI ID: 5863806
• Journal Information: Sov. At. Energy (Engl. Transl.); (United States), Journal Name: Sov. At. Energy (Engl. Transl.); (United States) Vol. 62:4; ISSN SATEA
• Country of Publication: United States
• Language: English

Related Subjects

050400* -- Nuclear Fuels-- Feed Processing
050800 -- Nuclear Fuels-- Spent Fuels Reprocessing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ACCURACY
ACTINIDE COMPOUNDS
ACTIVATION ENERGY
ALKANES
AQUEOUS SOLUTIONS
BUTYL PHOSPHATES
COMPARATIVE EVALUATIONS
COMPLEXOMETRY
DISPERSIONS
DODECANE
ENERGY
ESTERS
EXTRACTION
FUELS
HYDROCARBONS
HYDROGEN COMPOUNDS
INORGANIC ACIDS
ISOTHERMS
KEROSENE
LIQUID FUELS
MATHEMATICAL MODELS
MIXTURES
NEPTUNIUM COMPOUNDS
NITRATES
NITRIC ACID
NITROGEN COMPOUNDS
OPTIMIZATION
ORGANIC COMPOUNDS
ORGANIC PHOSPHORUS COMPOUNDS
ORGANIC SOLVENTS
OXYGEN COMPOUNDS
PETROLEUM PRODUCTS
PHOSPHORIC ACID ESTERS
PLUTONIUM COMPOUNDS
QUANTITY RATIO
SALTING-OUT AGENTS
SENSITIVITY ANALYSIS
SEPARATION PROCESSES
SOLUTIONS
SOLVENT EXTRACTION
SOLVENT PROPERTIES
SOLVENTS
TBP
TRANSURANIUM COMPOUNDS
URANIUM COMPOUNDS
URANYL COMPOUNDS
URANYL NITRATES
VALENCE