Modeling of aqueous and organic phase speciation for solvent extraction systems
Conference
·
OSTI ID:6432895
The TRUEX (TRansUranic EXtraction) solvent extraction process has the ability to remove, separate, and recover transuranic (TRU) elements from acidic nuclear waste solutions. A computer model of the TRUEX process is currently being developed for use in flowsheet design and process optimization. The correlations that are to be used in the model for generating extraction distribution ratios are based on chemical mass action principles and require calculation of aqueous and organic phase speciation. Aqueous phase activity coefficients are calculated using methods available in the literature, while the organic phase species are treated in terms of ideal associated solution theory. This approach is demonstrated for the extraction of HNO/sub 3/, HTcO/sub 4/, and americium nitrate by n-octyl(phenyl)-N,N-diisobutylcarbamoyl-methylphosphine oxide (CMPO)---the primary metal extractant in the TRUEX solvent. 23 refs., 5 figs.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6432895
- Report Number(s):
- CONF-890215-4; ON: DE89009803
- Country of Publication:
- United States
- Language:
- English
Similar Records
Hydrolytic and radiolytic degradation of O/phi/D (iB)CMPO; continuing studies
Transuranic decontamination of nitric acid solutions by the TRUEX solvent extraction process: preliminary development studies. [Octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide]
Recovery of plutonium and americium from chloride salt wastes by solvent extraction
Conference
·
Sat Oct 01 00:00:00 EDT 1988
· Sep. Sci. Technol.; (United States)
·
OSTI ID:6253677
Transuranic decontamination of nitric acid solutions by the TRUEX solvent extraction process: preliminary development studies. [Octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide]
Technical Report
·
Sun Jul 01 00:00:00 EDT 1984
·
OSTI ID:6696097
Recovery of plutonium and americium from chloride salt wastes by solvent extraction
Conference
·
Sat Oct 01 00:00:00 EDT 1988
· Sep. Sci. Technol.; (United States)
·
OSTI ID:6019466
Related Subjects
050800* -- Nuclear Fuels-- Spent Fuels Reprocessing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CHEMISTRY
400105 -- Separation Procedures
ACTINIDE COMPOUNDS
AMERICIUM COMPOUNDS
AMERICIUM NITRATES
ARRHENIUS EQUATION
EQUATIONS
EXTRACTION
HYDROGEN COMPOUNDS
INORGANIC ACIDS
KINETICS
MATHEMATICAL MODELS
NITRATES
NITRIC ACID
NITROGEN COMPOUNDS
OXYGEN COMPOUNDS
PHOSPHINE OXIDES
PHOSPHINES
PHOSPHORUS COMPOUNDS
REACTION KINETICS
REFRACTORY METAL COMPOUNDS
SEPARATION PROCESSES
SOLVENT EXTRACTION
SOLVENT PROPERTIES
TECHNETATES
TECHNETIUM COMPOUNDS
TRANSITION ELEMENT COMPOUNDS
TRANSPLUTONIUM COMPOUNDS
TRANSURANIUM COMPOUNDS
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CHEMISTRY
400105 -- Separation Procedures
ACTINIDE COMPOUNDS
AMERICIUM COMPOUNDS
AMERICIUM NITRATES
ARRHENIUS EQUATION
EQUATIONS
EXTRACTION
HYDROGEN COMPOUNDS
INORGANIC ACIDS
KINETICS
MATHEMATICAL MODELS
NITRATES
NITRIC ACID
NITROGEN COMPOUNDS
OXYGEN COMPOUNDS
PHOSPHINE OXIDES
PHOSPHINES
PHOSPHORUS COMPOUNDS
REACTION KINETICS
REFRACTORY METAL COMPOUNDS
SEPARATION PROCESSES
SOLVENT EXTRACTION
SOLVENT PROPERTIES
TECHNETATES
TECHNETIUM COMPOUNDS
TRANSITION ELEMENT COMPOUNDS
TRANSPLUTONIUM COMPOUNDS
TRANSURANIUM COMPOUNDS