SOLVENT EXTRACTION OF PLUTONIUM IN THE SYSTEM OF TRI-N-BUTYL PHOSPHINE OXIDE-CARBON TETRACHLORIDE AND NITRIC ACID SOLUTION
Journal Article
·
· J. Atomic Energy Soc. Japan
The distribution ratio of Fu(IV) and Fu(III) between nitric acid solution and tri-n-buty- phosphine oxide solution diluted with carbcn tetrachloride was determined in the range of nitric acid concentration from 0.5M to 10M and tri-n-butyl phosphine oxide concentration from 1 x 10/sup -4/M to 3 x 10/sup -1/(M. It was found that plutonium can be easily extracted from the irradiated urantum under the suitable conditions of extraction. (auth)
- Research Organization:
- Atomic Energy Research Inst., Tokyo
- Sponsoring Organization:
- USDOE
- NSA Number:
- NSA-14-024205
- OSTI ID:
- 4143390
- Journal Information:
- J. Atomic Energy Soc. Japan, Journal Name: J. Atomic Energy Soc. Japan Vol. Vol: 2
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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