Abstract
The partitioning and recovery of237Np from three types of simulated high level waste solutions originating from PUREX processing of spent nuclear fuels such as sulfate bearing high level waste (SB-HLW), HLW from a pressurised heavy water reactor (PHWR-HLW) and from a fast breeder reactor (FBR-HLW) have been carried out using a mixture of 0.2M CMPO and 1.2M TBP in dodecane. Quantitative extraction of neptunium was possible by either oxidizing it to the hexavalent state keeping K2Cr2O7 at 0.01M concentration or by reducing it to tetravalent state keeping Fe2+ at 0.02M concentration. Stripping of neptunium was carried out using different reagents, such as dilute nitric acid, oxalic acid and sodium carbonate. Almost quantitative recovery of neptunium has been achieved during these studies.
This is a preview of subscription content, log in via an institution to check access.
Similar content being viewed by others
References
J.N. Mathur, M.S. Murali, P.R. Natarajan, L.P. Badheka, A. Banerji, A. Ramanujam, P.S. Dhami, V. Gopalakrishnan, R.K. Dhumwad, M.K. Rao,Waste Management, 13 (1993) 317.
J.N. Mathur, M.S. Murali, R.H. Iyer, A. Ramanujam, P.S. Dhami, V. Gopalakrishnan, M.K. Rao, L.P. Badheka, A. Banerji,Nuclear Technology, 109 (1995) 216.
W.W. Schulz, E.P. Horwitz,Sep. Sci. Technol., 23 (1988) 1191.
E.P. Horwitz, R. Chiarizia, R.C. Gatrone,Solvent Extr. Ion Exch. 6 (1988) 93.
M. Ozawa, S. Nemoto, A. Togaski, T. Kawata, K. Onisi,Solvent Extr. Ion Exch., 10 (1992) 829.
V. Gopalakrishnan, P.S. Dhami, A. Ramanujam, M.V. Balarama Krishna, M.S. Murali, J.N. Mathur, A.K. Bauri, A. Banerji,J. Radioanal. Nucl. Chem. Articles, 191 (1995) 279.
Z.J. Kolarik, E.P. Horwitz,Solvent Extr. Ion Exch., 6 (1988) 247.
B.J. Mincher,Solvent Extr. Ion Exch., 7 (1989) 645.
S. Nagasaki, K. Kinoshita, D.S. Wisnbroto, Y. Enokida, A. Suzuki,J. Nucl. Sci. Tech., 29 (1992) 671.
Y. Morita, M. Kubota,Solvent Extr. Ion Exch., 6 (1988) 233.
Y. Morita, I. Yamaguchi, Y. Kondo, K. Shirahashi, Yamagishi, T. Fujiwara, M. Kubota, Proc. of Technical Committee on “Safety and Environmental Aspects of Partitioning and Transmutation of Actinides and Fission Products”, Vienna (1993), TECDOC-783 (1995).
J.N. Mathur, M.S. Murali, P.R. Natarajan, L.P. Badheka, A. Banerji,Talanta, 39 (1992) 493.
Author information
Authors and Affiliations
Rights and permissions
About this article
Cite this article
Mathur, J.N., Murali, M.S., Balarama Krishna, M.V. et al. Recovery of neptunium from highly radioactive waste solutions of PUREX origin using CMPO. Journal of Radioanalytical and Nuclear Chemistry Letters 213, 419–429 (1996). https://doi.org/10.1007/BF02162221
Received:
Accepted:
Issue Date:
DOI: https://doi.org/10.1007/BF02162221