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- Title
Studies on solubility of TBP in aqueous solutions of fuel reprocessing.
- Authors
Velavendan, P.; Ganesh, S.; Pandey, N.; Geetha, R.; Ahmed, M.; Kamachi Mudali, U.; Natarajan, R.
- Abstract
In nuclear technology, tri- n-butyl phosphate (TBP) diluted with a hydrocarbon diluent such as n-dodecane or NPH is the most frequently used solvent in liquid-liquid extraction for fuel reprocessing. This extraction, known as the plutonium uranium refining by extraction, is still considered as the most dominant process for the extraction of uranium and plutonium from irradiated fuels. The solubility of pure TBP in water is about 0.4 g/L at 25 °C. This is enough to create trouble during evaporation of raffinate and product solutions. Solubility data for undiluted TBP and TBP (diluted in inert hydrocarbon diluent) in various concentrations of nitric acid is not adequate in the literature. The solubility data generated in the present study provide complete information on the solubility of TBP in various nitric acid concentrations (0-15.7 M) at room temperature. The effect of heavy metal ion concentration such as uranium and various fission products on the solubility of TBP in nitric acid is also presented. The results obtained from gas chromatographic technique were compared with spectrophotometric technique by converting the organic phosphate into inorganic phosphate. The generated data is of direct relevance to reprocessing applications.
- Subjects
REACTOR fuel reprocessing; BUTYL group; SOLUBILITY; AQUEOUS solutions; EXTRACTION (Chemistry); PLUTONIUM; URANIUM; GAS chromatography; FLAME ionization detectors
- Publication
Journal of Radioanalytical & Nuclear Chemistry, 2013, Vol 295, Issue 2, p1113
- ISSN
0236-5731
- Publication type
Article
- DOI
10.1007/s10967-012-1945-1