Reaction of uranyl nitrate solutions with carboxylic acid cation exchange resins at 30, 40, and 50/sup 0/C. [Amberlite IRC-72; Duolite C-464]
An investigation of the reaction of uranyl nitrate solution with Amberlite IRC-72 and with Duolite C-464 resin was conducted under equilibrium conditions for application to a high-temperature gas-cooled reactor fuel refabrication facility. Test series were conducted at constant nitrate ion concentrations in which the uranyl ion distribution between the phases was varied from values corresponding to approximately 10% resin loading to those for essentially complete resin loading. Equilibrium quotients, calculated as the metathetical exchange of uranyl ion for replaceable hydrogen in the resin phase, were calculated for each test series over the nitrate ion concentration range of 0.2 to 2.0 N and at temperatures of 30, 40, and 50/sup 0/C. These values varied with nitrate ion concentration but were relatively insensitive to changes in temperature.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 6418684
- Report Number(s):
- ORNL/TM-6611
- Country of Publication:
- United States
- Language:
- English
Similar Records
Distribution of iron during full loading of amberlite IRC-72 resin with uranium from nitrate solutions at 30/sup 0/C
Reaction of uranyl nitrate solutions with amberlite IRC-72 cation exchange resin at 30/sup 0/C: a kinetic investigation for the HTGR fuel recycle plant
Decontamination of Dissolved Salt Solution from Tank 19F Using Duolite CS-100 and Amberlite IRC-718 Resins
Technical Report
·
Sun Dec 31 23:00:00 EST 1978
·
OSTI ID:6566314
Reaction of uranyl nitrate solutions with amberlite IRC-72 cation exchange resin at 30/sup 0/C: a kinetic investigation for the HTGR fuel recycle plant
Technical Report
·
Sat Dec 31 23:00:00 EST 1977
·
OSTI ID:5268040
Decontamination of Dissolved Salt Solution from Tank 19F Using Duolite CS-100 and Amberlite IRC-718 Resins
Technical Report
·
Wed Oct 17 00:00:00 EDT 2001
·
OSTI ID:787807
Related Subjects
050700* -- Nuclear Fuels-- Fuels Production & Properties
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CHEMISTRY
400105 -- Separation Procedures
ACTINIDE COMPOUNDS
CHEMICAL REACTIONS
DISPERSIONS
EQUILIBRIUM
FUEL CYCLE
FUEL FABRICATION PLANTS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
ION EXCHANGE
ION EXCHANGE MATERIALS
MIXTURES
NITRATES
NITROGEN COMPOUNDS
NUCLEAR FACILITIES
ORGANIC COMPOUNDS
ORGANIC POLYMERS
OXYGEN COMPOUNDS
PETROCHEMICALS
PETROLEUM PRODUCTS
POLYMERS
QUANTITY RATIO
REACTORS
RESINS
SOLUTIONS
SORPTIVE PROPERTIES
SURFACE PROPERTIES
TEMPERATURE DEPENDENCE
URANIUM COMPOUNDS
URANYL COMPOUNDS
URANYL NITRATES
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CHEMISTRY
400105 -- Separation Procedures
ACTINIDE COMPOUNDS
CHEMICAL REACTIONS
DISPERSIONS
EQUILIBRIUM
FUEL CYCLE
FUEL FABRICATION PLANTS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
ION EXCHANGE
ION EXCHANGE MATERIALS
MIXTURES
NITRATES
NITROGEN COMPOUNDS
NUCLEAR FACILITIES
ORGANIC COMPOUNDS
ORGANIC POLYMERS
OXYGEN COMPOUNDS
PETROCHEMICALS
PETROLEUM PRODUCTS
POLYMERS
QUANTITY RATIO
REACTORS
RESINS
SOLUTIONS
SORPTIVE PROPERTIES
SURFACE PROPERTIES
TEMPERATURE DEPENDENCE
URANIUM COMPOUNDS
URANYL COMPOUNDS
URANYL NITRATES