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Abstract
Tri-n-Butyl Phosphate has been found to be an extractant-par-excellence for nuclear fuel reprocessing. It has a unique combination of physical and chemical proerties and is commercially available at relatively low cost. However, the other homologues of TBP-with branched alkyl chains as well as linear alkyl chains-do possess advantages for specific applications that merit attention. Thus, a relative comparison of the extraction properties of the trialkyl phosphates is rewarding, both from a fundamental as well as technological point of view. The present review attempts to survey the data reported and the understanding generated on the extraction of actinides by trialkyl phosphates, with an emphasis on the elements U, Th and Pu, taking into account their importance derived from their primary role in the nuclear fuel cycles. While reviewing the data, emphasis is placed on data measured for extraction by 1.09 M solution of the extrac-tant, from nitric acid medium.