THE URANIUM(VI)-NITRATE-TRIBUTYL PHOSPHATE SOLVENT EXTRACTION SYSTEM. A THERMODYNAMIC ANALYSIS
Technical Report
·
OSTI ID:4086099
ABS>A thermodynamic analysis of a solvent extraction system (UO/sub 2/ (NO/sub 3/)/sub 2/-TBP) is presented. Theoretical equations are derived, or appropriately modified, and compared with published experimental data. Some of the effects taken into account are: extraction of nitric acid, incomplete dissociation of this acid, hydration of the TBP, and aqueous complexing and hydrolysis of the uranyl ion. The treatment may be applied also to other systems of coextraction, such as plutonium with uranium nitrate into TBP. (auth)
- Research Organization:
- Israel. Atomic Energy Commission, Tel-Aviv
- NSA Number:
- NSA-15-011054
- OSTI ID:
- 4086099
- Report Number(s):
- NP-9733; IA/582
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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