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Spent fuel recycling and conditioning topic of U.S.-Japan meeting
Officials with the Department of Energy’s Office of Environmental Management discussed spent nuclear fuel recycling and conditioning with counterparts from Japan during the 13th U.S.-Japan Technical Meeting of the Civil Nuclear Energy Research and Development Working Group, held recently in Santa Fe, N.M.
A. Suresh, N. L. Sreenivasan, Robert Selvan, M. P. Antony, T. G. Srinivasan, S. B. Koganti, P. R. Vasudeva Rao
Nuclear Technology | Volume 167 | Number 2 | August 2009 | Pages 333-338
Technical Note | Reprocessing | doi.org/10.13182/NT09-A8968
Articles are hosted by Taylor and Francis Online.
Tri-n-butyl phosphate (TBP) is being employed as the extractant for the processing of nuclear materials all over the world. However, some of its limitations such as third-phase formation, aqueous solubility, chemical and radiation degradation, etc., affect the performance of TBP-based extraction processes. Hence, there is a need to identify alternative extractants that do not possess the disadvantages of TBP but retain the desirable properties of TBP. In this connection, higher homologues of TBP such as tri-n-amyl phosphate (TAP) and some of its isomers are considered to be important for various solvent extraction processes. Batch extraction studies have been carried out on the extraction of U(VI) by 1.1 M solutions of TBP and TAP in n-dodecane as well as heavy normal paraffin (HNP), and the results are reported in this paper. Extraction of U(VI) by 1.1 M TAP/HNP under high solvent loading conditions and subsequent stripping of U(VI) by 0.01 M HNO3 from loaded 1.1 M TAP/HNP in a countercurrent mode were also carried out with an ejector mixer-settler. This paper describes the results of these mixer-settler runs. Results revealed the suitability of higher homologues of TBP for reprocessing applications.