Recovery of plutonium from carbonate wash solutions
Creators
- 1. Indira Gandhi Centre for Atomic Research, Kalpakkam, Tamil Nadu (India). Reprocessing Group
Description
A novel method has been developed for recovery of plutonium and uranium from carbonate wash solutions generated during solvent wash process involved in the reprocessing of high burn up FBTR fuel. The proposed method involves a selective coprecipitation of Pu and U by adding ammonium hydroxide to the pre acidified carbonate wash solution. Substantial removal of DBP by successive steps of coprecipitation, completely eliminates the possibility of undesired solid formation which is mainly due to the presence of high content of DBP. By adopting this method, an excellent decontamination factor for DBP has been achieved without any crud/solid formation. Phosphate content in the final oxide product meets the product specifications. Flowsheet condition necessary for the recovery process for plutonium from the aqueous carbonate solution is formulated and adopted in the CORAL facility. (author)
Additional details
Publishing Information
- Journal Title
- Journal of Radioanalytical and Nuclear Chemistry
- Journal Volume
- 284
- Journal Issue
- 1
- Journal Page Range
- p. 151-156
- ISSN
- 0236-5731
- CODEN
- JRNCDM
INIS
- Country of Publication
- Hungary
- Country of Input or Organization
- Hungary
- INIS RN
- 41041940
- Subject category
- S37: INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY; S54: ENVIRONMENTAL SCIENCES;
- Descriptors DEI
- AMMONIUM HYDROXIDES; CARBONATES; DECONTAMINATION; PLUTONIUM; URANIUM
- Descriptors DEC
- ACTINIDES; AMMONIUM COMPOUNDS; CARBON COMPOUNDS; CLEANING; ELEMENTS; HYDROGEN COMPOUNDS; HYDROXIDES; METALS; OXYGEN COMPOUNDS; TRANSURANIUM ELEMENTS
Optional Information
- Notes
- 18 refs.