Comparison of Anion Exchange Resins for Recovering Plutonium from Nitric Acid Waste
- 1 November 1979
- journal article
- research article
- Published by Taylor & Francis in Nuclear Technology
- Vol. 46 (1) , 105-109
- https://doi.org/10.13182/nt79-a32383
Abstract
Microreticular and macroreticular anion exchange resins were compared for their capability of recovering plutonium from nitric acid waste streams. Plutonium breakthrough capacity and elution behavior of the resins were determined as a function of resin properties. Small-bead microreticular resins with a polystyrene matrix containing 4% divinylbenzene cross-linkage showed the best performance. Of the 20- to 50-mesh resins, the macroreticular resin, Amberlite IRA-938, gave the highest plutonium breakthrough capacity and eluted plutonium the fastest.Keywords
This publication has 3 references indexed in Scilit:
- Evaluation of anion exchange resins for plutonium-uranium separations in nitric acidJournal of Radioanalytical and Nuclear Chemistry, 1978
- Evaluation of anion exchange resins for processing plutonium--neptunium residuesPublished by Office of Scientific and Technical Information (OSTI) ,1977
- THE RECOVERY, PURIFICATION, AND CONCENTRATION OF PLUTONIUM BY ANION EXCHANGE IN NITRIC ACIDPublished by Office of Scientific and Technical Information (OSTI) ,1959