Studies on the acidification of carbonate waste stream for separation of di-butyl phosphate and recovery of metal
Author:
Mishra Satyabrata1, Pankaj 1, Patra Chayan1, Ghosh Debojyoti1, Desigan Narasimhan1, Velavendan Periyakaruppan1, Venkatesan Konda Athmaram1, Krishnamurthy Ananthasivan1
Affiliation:
1. Reprocessing Group , Indira Gandhi Centre for Atomic Research , Kalpakkam , 603102 , India
Abstract
Abstract
The aqueous waste generated during the treatment of Purex lean organic phase with alkaline carbonate solution contains washable degradation products and actinides in the form of carbonate complex. Management of such aqueous waste demands quantitative removal of the main degradation product, dibutyl phosphate (HDBP) and actinides from aqueous solution. In this context, batch studies have been carried out on the separation of HDBP from aqueous solution using n-dodecane (n-DD). For this purpose, the extraction behaviour of HDBP in n-DD was studied after acidification of alkaline carbonate solution with nitric acid. The studies with simulated waste containing HDBP and U(VI) nitrate showed the loss of U(VI) as precipitate during acidification as the uranium–DBP was poorly soluble in aqueous phase. However, the loss of U(VI) decreased with increase of aqueous phase acidity showing that the adjusted acidity of the carbonate waste plays an important role in the recovery of actinides.
Publisher
Walter de Gruyter GmbH
Subject
Physical and Theoretical Chemistry
Reference21 articles.
1. McKay, H. A. C., Miles, J. H., Swanson, J. L. The Purex process. In Science and Technology of Tri Butyl Phosphate; Schulz, W. W., Burger, L. L., Navratil, J. D., Eds.; CRS Press: Boca Raton, 3, 1984; pp. 55–90. 2. Pavia, A. P., Malik, P. Recent advances on the chemistry of solvent extraction applied to the reprocessing of spent nuclear fuels and radioactive wastes. J. Radioanal. Nucl. Chem. 2004, 261, 485–496; https://doi.org/10.1023/b:jrnc.0000034890.23325.b5. 3. Satyabrata, M., Mallika, C., Pandey, N. K., Mudali, U. K., Natarajan, R. Effect of radiolysis in altering the physiochemical and metal retention properties of solvent-diluent-acid systems. Sep. Sci. Technol. 2015, 50, 1671–1676; https://doi.org/10.1080/01496395.2014.988359. 4. Satyabrata, M., Desigan, N., Venkatesan, K. A., Ananthasivan, K. Hydrolytic degradation of tri-iso-amyl phosphate-dodecane system. J. Mol. Liq. 2021, 334, 116512; https://doi.org/10.1016/j.molliq.2021.116512. 5. Natarajan, R. Reprocessing of spent fast reactor nuclear fuels. In Woodhead Publishing Series in Energy, Reprocessing and Recycling of Spent Nuclear Fuel; Taylor, R., Ed.; Woodhead Publishing Series in Energy: Oxford, 2015; pp. 213–243.
|
|