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- W51598456 abstract "The Savannah River Site (SRS) has recovered {sup 237}Np from reactor fuel that is currently being processed into NpO{sub 2} for future production of {sup 238}Pu. Several purification flowsheets have been utilized. An oxidizing solvent-extraction (SX) flowsheet was used to remove Fe, sulfate ion, and Th while simultaneously {sup 237}Np, {sup 238}Pu, u, and nonradioactive Ce(IV) was extracted into the tributyl phosphate (TBP) based organic solvent. A reducing SX flowsheet (second pass) removed the Ce and Pu and recovered both Np and U. The oxidizing flowsheet was necessary for solutions that contained excessive amounts of sulfate ion. Anion exchange was used to perform final purification of Np from Pu, U, and various non-actinide impurities. The Np(IV) in the purified solution was then oxalate-precipitated and calcined to an oxide for shipment to other facilities for storage and future target fabrication. Performance details of the SX purification and process difficulties are discussed. (authors)" @default.
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- W51598456 date "2008-07-01" @default.
- W51598456 modified "2023-09-23" @default.
- W51598456 title "Solvent-extraction purification of neptunium" @default.
- W51598456 hasPublicationYear "2008" @default.
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