Modeling of distribution and speciation of plutonium in the Urex extraction system
- Radiation Center, Oregon State University, Corvallis, OR 97331-5903 (United States)
- Argonne National Laboratory, Chemical Sciences and Engineering Division, Argonne, IL 60439-4837 (United States)
The PUREX extraction process is used worldwide to recover uranium and plutonium from dissolved spent nuclear fuel using the tributylphosphate-nitric acid extraction system. In the recent decade, significant research progress was achieved with the aim to modify this system by addition of a salt-free agent to optimize stripping of plutonium from the tributylphosphate (TBP) extraction product (UREX). Experimental results on the extraction of Pu(IV) with and without acetohydroxamic acid in the HNO{sub 3}/TBP (30 vol %) were used for the development of a thermodynamic model of distribution and speciation of Pu(IV) in this separation process. Extraction constants for several sets of nitric acid, nitrate, and acetohydroxamic acid concentrations were used to model the obtained data. The extraction model AMUSE (Argonne Model for Universal Solvent Extraction) was employed in our calculations. (authors)
- Research Organization:
- Chemical Sciences Division, Oak Ridge National Laboratory (United States)
- OSTI ID:
- 21230367
- Resource Relation:
- Conference: ISEC 2008: International Solvent Extraction Conference on Solvent Extraction: Fundamentals to Industrial Applications, Tucson, AZ (United States), 15-19 Sep 2008; Other Information: Country of input: France; 13 refs; Related Information: In: Proceedings of ISEC 2008, International Solvent Extraction Conference - Solvent Extraction: Fundamentals to Industrial Applications, by Moyer, Bruce A. (ed.), 1740 pages.
- Country of Publication:
- United States
- Language:
- English
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