Tri-iso-amyl Phosphate: a potential extractant for the reprocessing of spent nuclear fuels

A solution of TBP diluted with n-alkane diluents (1.1M) has been utilized as a versatile solvent in various separation processes and for the reprocessing of thermal and fast reactor fuels (PUREX process). However, the experience gained in the past several decades has revealed few drawbacks that are of concern in various separation processes. Studies reveal that TiAP based solvent does not form third phase during the extraction of Pu(IV) from nitric acid media. Co-extraction of U(VI) and Pu(IV) by TiAP indicate that it is possible to achieve maximum loading in the organic phase without any phase splitting. These studies also indicate that the extraction behaviour of fissions products by TiAP is comparable to that of TBP and the radiolytic degradation behaviour of TiAP is not very much different from that of TBP. The lower aqueous phase solubility of TiAP has a great advantage in minimising runway reactions. Based on these studies it can be concluded that it is possible to employ TiAP as an alternate extractant to TBP for fast reactor fuel reprocessing