Separation of dilute plutonium(IV) from nitric acid solutions via Reillex HPQ anion exchange resin

• Published in: Separation science and technology Vol. 60; no. 12; pp. 1502 - 1510
• Main Authors: Mills, Matthew S., Mills, Sasha C., Carter, Rebecca A., Lascola, Robert J., Armstrong, Christopher R.
• Format: Journal Article
• Language: English
• Published: Taylor & Francis 13.08.2025
• Subjects: anion exchange; nuclear fuel cycle; Plutonium separations; radiochemical separations
• ISSN: 0149-6395; 1520-5754
• DOI: 10.1080/01496395.2025.2509139

Anion exchange is a common method for the separation of plutonium (Pu) in aqueous systems, providing high recovery and decontamination from impurities. Reillex HPQ anion exchange resin has been used around the Department of Energy complex in this application for decades but has typically been used for Pu feed concentrations greater than 1 g/L. It is desirable to recover Pu at more dilute concentrations from a dissolved used fuel or target element, for example. In this work, the performance of Reillex HPQ anion exchange resin was characterized with feed solutions of ca. 0.24 g/L Pu. A significant reduction in the performance of the resin was realized with this dilute concentration relative to a feed solution of 2.35 g/L Pu with similar feed flow rates and the same resin column, likely due to the increased driving force for mass transfer with a higher feed concentration. The maximum capacity of Reillex HPQ resin for Pu can be improved by reducing the flow rate and increasing the feed Pu concentration. The breakthrough point of Pu can be improved in the same manner and by increasing the resin bed height. Diffusion of Pu into the resin was illustrated to be the rate limiting step.