An Alternative Solvent Extraction Flowsheet for Separating 237Np from 238Pu for Space Power Applications. Issue 4 (7th June 2022)

• Record Type: Journal Article
• Authors: Sarsfield, M. J.; Carrott, M. J.; Maher, C. J.; Mason, C.; Sanderson, R.; Taylor, R. J.; Tinsley, T. P.; Whittaker, D.; Woodhead, D. A.
• Is Part Of: Solvent extraction and ion exchange. Volume 40:Issue 4(2022)
• Page Start: 349
• Page End: 365
• Publication Date: 2022-06-07
• Subjects: Neptunium -- plutonium solvent extraction -- hydroxylamine -- kinetics -- modelling; Solvent extraction -- Periodicals; Ion exchange -- Periodicals; 660.284248
• DOI: 10.1080/07366299.2021.1939177
• Languages: English
• ISSNs: 0736-6299

Abstract

ABSTRACT: The production of 238 Pu from 237 Np, to the specifications required for space flight, requires the separation of plutonium from neptunium and a range of fission products. The valuable neptunium is then recycled into targets for further irradiation. At Oak Ridge National Laboratory (ORNL), a solvent extraction process has been developed to separate neptunium and plutonium that uses sodium nitrite to control the neptunium oxidation. This results in a neptunium product contaminated with sodium, which needs to be removed prior to recycling. We have developed a separation process that results in a sodium-free neptunium product with very low levels of plutonium contamination, there by reducing the number of purification steps and thus simplifying the process.