Solvent extraction studies of 10% TBP flowsheets in the solvent extraction test facility using irradiated fuel from the Fast Flux Test Facility
Two solvent extraction experiments were made in the Solvent Extraction Test Facility (SETF) during Campaign 10 to continue the evaluation of: (1) a computer control system for the coextraction-coscrub contractor; and (2) a partitioning technique that separates uranium and plutonium without the aid of chemical reductants. The Fast Flux Test Facility (FFTF) fuel used in this campaign had burnups of {approximately}55 and {approximately}60 (average) MWd/kg. During both experiments, the computer control system successfully maintained stable, efficient operation. The control system used an in-line photometer to monitor the plutonium concentration in the extraction section; and based on this data, it adjusted the addition rate of the extractant to maintain high loadings of heavy metal in the solvent and low raffinate losses. The uranium and plutonium partitioning relied entirely on the differences between the U(VI) and Pu(IV) distribution coefficients (since no reductant was used to adjust the plutonium valence). In order to enhance this difference, the TBP concentration and operating temperature were relatively low in comparison to traditional Purex flowsheets. Final product purities of 99{percent} were achieved for both the uranium and plutonium in one cycle of partitioning.
- Research Organization:
- Oak Ridge National Lab., TN (United States)
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 714339
- Report Number(s):
- ORNL/TM--10266; ON: DE88007864
- Country of Publication:
- United States
- Language:
- English
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