Recovery of transplutonium elements from nuclear reactor waste
A method of separating actinide values from nitric acid waste solutions resulting from reprocessing of irradiated nuclear fuels comprises oxalate precipitation of the major portion of actinide and lanthanide values to provide a trivalent fraction suitable for subsequent actinide/lanthanide partition, exchange of actinide and lanthanide values in the supernate onto a suitable cation exchange resin to provide an intermediate-lived raffinate waste stream substantially free of actinides, and elution of the actinide values from the exchange resin. The eluate is then used to dissolve the trivalent oxalate fraction prior to actinide/lanthanide partition or may be combined with the reprocessing waste stream and recycled. 5 claims, 2 figures.
- Assignee:
- Energy Research and Development Administration
- Patent Number(s):
- US 4025602
- Application Number:
- TRN: 78-001397
- OSTI ID:
- 5315471
- Resource Relation:
- Patent File Date: Filed date 25 May 1976; Other Information: PAT-APPL-689,888
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
ACTINIDES
SEPARATION PROCESSES
FUEL REPROCESSING PLANTS
RADIOACTIVE WASTE PROCESSING
ION EXCHANGE MATERIALS
LIQUID WASTES
NITRIC ACID
OXALATES
PRECIPITATION
RARE EARTHS
TRANSPLUTONIUM ELEMENTS
CARBOXYLIC ACID SALTS
ELEMENTS
HYDROGEN COMPOUNDS
INORGANIC ACIDS
MANAGEMENT
METALS
NUCLEAR FACILITIES
PROCESSING
TRANSURANIUM ELEMENTS
WASTE MANAGEMENT
WASTE PROCESSING
WASTES
052001* - Nuclear Fuels- Waste Processing