skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Solvent-extraction purification of neptunium

Conference ·
OSTI ID:21230370
 [1];  [2]
  1. Savannah River National Laboratory, Actinide and Chemical Technology Section, 773-A Aiken, SC 29808 (United States)
  2. H Canyon Engineering, 221-H, Aiken, SC 29808 (United States)

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)

Research Organization:
Chemical Sciences Division, Oak Ridge National Laboratory (United States)
OSTI ID:
21230370
Resource Relation:
Conference: ISEC 2008: International Solvent Extraction Conference on Solvent Extraction: Fundamentals to Industrial Applications, Tucson, AZ (United States), 15-19 Sep 2008; Other Information: Country of input: France; 6 refs; Related Information: In: Proceedings of ISEC 2008, International Solvent Extraction Conference - Solvent Extraction: Fundamentals to Industrial Applications, by Moyer, Bruce A. (ed.), 1740 pages.
Country of Publication:
United States
Language:
English