Published November 1979
| Version v1
Journal article
Comparison of anion exchange resins for recovering plutonium from nitric acid waste
Description
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
Additional details
Publishing Information
- Journal Title
- Nucl. Technol.
- Journal Volume
- 46
- Journal Issue
- 1
- Series
- Nucl. Technol.
- Journal Page Range
- 105-109
- ISSN
- 0029-5450
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11523287
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Descriptors DEI
- COMPARATIVE EVALUATIONS; ION EXCHANGE; NITRIC ACID; ORGANIC ION EXCHANGERS; PLUTONIUM; POLYVINYLS; RADIOACTIVE WASTE PROCESSING; RESINS
- Descriptors DEC
- ACTINIDES; ELEMENTS; HYDROGEN COMPOUNDS; INORGANIC ACIDS; ION EXCHANGE MATERIALS; MANAGEMENT; METALS; NITROGEN COMPOUNDS; ORGANIC COMPOUNDS; ORGANIC POLYMERS; OXYGEN COMPOUNDS; POLYMERS; TRANSURANIUM ELEMENTS; WASTE MANAGEMENT; WASTE PROCESSING