Method of uranium reclamation from aqueous systems by reactive ion exchange. [US DOE patent application; anion exchange resin of copolymerized divinyl-benzene and styrene having quarternary ammonium groups and bicarbonate ligands]
Patent
·
OSTI ID:5040906
A reactive ion exchange method for separation and recovery of values of uranium, neptunium, plutonium, or americium from substantially neutral aqueous systems of said metals comprises contacting said system with an effective amount of a basic anion exchange resin of copolymerized divinyl-benzene and styrene having quarternary ammonium groups and bicarbonate ligands to achieve nearly 100% sorption of said actinyl ion onto said resin and an aqueous system practically free of said actinyl ions. The method is operational over an extensive range of concentrations from about 10/sup -6/ M to 1.0 M actinyl ion and a pH range of about 4 to 7. The method has particulr application to treatment of waste streams from Purex-type nuclear fuel reprocessing facilities and hydrometallurgical processes involving U, Np, P, or Am.
- DOE Contract Number:
- W-7405-ENG-26
- Assignee:
- Dept. of Energy
- Patent Number(s):
- None
- Application Number:
- ON: DE82020871
- OSTI ID:
- 5040906
- Country of Publication:
- United States
- Language:
- English
Similar Records
TRACER TECHNIQUES FOR THE DETERMINATION OF MONOMER REACTIVITY RATIOS. II. MONOMER REACTIVITY RATIOS IN COPOLYMERIZATIONS WITH DIVINYL MONOMERS
RECOVERY OF NEPTUNIUM FROM PUREX WASTE BY AN AGITATED BED OF ANION EXCHANGE RESIN
Recovery, concentration, and solidification of europium by ion exchange from a dilute process stream
Journal Article
·
Sun Jan 31 23:00:00 EST 1960
· J. Polymer Sci.
·
OSTI ID:4180328
RECOVERY OF NEPTUNIUM FROM PUREX WASTE BY AN AGITATED BED OF ANION EXCHANGE RESIN
Technical Report
·
Sun Jan 31 23:00:00 EST 1960
·
OSTI ID:4690460
Recovery, concentration, and solidification of europium by ion exchange from a dilute process stream
Technical Report
·
Mon Nov 30 23:00:00 EST 1987
·
OSTI ID:5698340
Related Subjects
052001 -- Nuclear Fuels-- Waste Processing
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CHEMISTRY
400105* -- Separation Procedures
ACTINIDES
AMERICIUM
AQUEOUS SOLUTIONS
DISPERSIONS
ELEMENTS
EXTRACTIVE METALLURGY
HYDROMETALLURGY
ION EXCHANGE
ION EXCHANGE MATERIALS
MANAGEMENT
MATERIALS
MATERIALS RECOVERY
METALLURGY
METALS
MIXTURES
NEPTUNIUM
ORGANIC COMPOUNDS
ORGANIC ION EXCHANGERS
ORGANIC POLYMERS
PETROCHEMICALS
PETROLEUM PRODUCTS
PH VALUE
PLUTONIUM
POLYMERS
POLYOLEFINS
POLYSTYRENE-DVB
PROCESSING
PUREX PROCESS
RADIOACTIVE WASTE PROCESSING
RECOVERY
REPROCESSING
RESINS
SEPARATION PROCESSES
SOLUTIONS
TRANSPLUTONIUM ELEMENTS
TRANSURANIUM ELEMENTS
URANIUM
WASTE MANAGEMENT
WASTE PROCESSING
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CHEMISTRY
400105* -- Separation Procedures
ACTINIDES
AMERICIUM
AQUEOUS SOLUTIONS
DISPERSIONS
ELEMENTS
EXTRACTIVE METALLURGY
HYDROMETALLURGY
ION EXCHANGE
ION EXCHANGE MATERIALS
MANAGEMENT
MATERIALS
MATERIALS RECOVERY
METALLURGY
METALS
MIXTURES
NEPTUNIUM
ORGANIC COMPOUNDS
ORGANIC ION EXCHANGERS
ORGANIC POLYMERS
PETROCHEMICALS
PETROLEUM PRODUCTS
PH VALUE
PLUTONIUM
POLYMERS
POLYOLEFINS
POLYSTYRENE-DVB
PROCESSING
PUREX PROCESS
RADIOACTIVE WASTE PROCESSING
RECOVERY
REPROCESSING
RESINS
SEPARATION PROCESSES
SOLUTIONS
TRANSPLUTONIUM ELEMENTS
TRANSURANIUM ELEMENTS
URANIUM
WASTE MANAGEMENT
WASTE PROCESSING