Abstract: Ferric ions are added into the aqueous feed of a plutonium scrap recovery process that employs a tributyl phosphate extractant. Radiolytic degradation products of tributyl phosphate such as dibutyl phosphate form a solid precipitate with iron and are removed from the extraction stages via the waste stream. Consequently, the solvent extraction characteristics are improved, particularly in respect to minimizing the formation of nonstrippable plutonium complexes in the stripping stages. The method is expected to be also applicable to the partitioning of plutonium and uranium in a scrap recovery process.

Abstract: A falling film evaporator including a vertically oriented pipe heated exteriorly by a steam jacket and interiorly by a finned steam tube, all heating surfaces of the pipe and steam tube being formed of a material wet by water such as stainless steel, and packing within the pipe consisting of Raschig rings formed of a material that is not wet by water such as polyvinylidene fluoride.

Abstract: A method for improving the extraction properties of a tributyl phosphate extractant used for reprocessing irradiated nuclear reactor fuel (Purex Process) containing degradation products of tributyl phosphate by contacting the extractant with diazomethane in a suitable solvent whereby the degradation products are esterified to triester phosphates which have extraction properties similar to those of tributyl phosphate.