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 · Sun Jan 01 04:00:00 EST 1978

DOI:https://doi.org/10.2172/5268040· OSTI ID:5268040

Shaffer, J. H.; Shockley, W. E.

A kinetic investigation of the reaction of uranyl nitrate solution with Amberlite IRC-72 cation exchange resin was conducted at 30/sup 0/C under conditions similar to those anticipated for a High-Temperature Gas-Cooled Reactor fuel refabrication facility. A simplified mass transfer analogue expression was developed to evaluate the effects of process parameters on the resin loading rate. Correlation of the experimental data with the integrated rate expression depended only on the determination of the reaction velocity constant and the limiting distribution coefficient for uranium in the system. 5 tables, 4 figs.

• Research Organization: ORNL (Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States))
• Sponsoring Organization: USDOE
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5268040
• Report Number(s): ORNL/TM-5866
• Country of Publication: United States
• Language: English

Related Subjects

050800* -- Nuclear Fuels-- Spent Fuels Reprocessing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CHEMISTRY
400202 -- Isotope Effects
Isotope Exchange
& Isotope Separation
ACTINIDE COMPOUNDS
ADSORPTION
AQUEOUS SOLUTIONS
CATIONS
CHARGED PARTICLES
CHEMICAL REACTION KINETICS
CORRELATIONS
DISPERSIONS
FUEL CYCLE
FUEL FABRICATION PLANTS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
ION EXCHANGE MATERIALS
IONS
KINETICS
MIXTURES
NITRATES
NITROGEN COMPOUNDS
NUCLEAR FACILITIES
ORGANIC COMPOUNDS
ORGANIC POLYMERS
OXYGEN COMPOUNDS
PETROCHEMICALS
PETROLEUM PRODUCTS
POLYMERS
REACTION KINETICS
REACTORS
RESINS
SOLUTIONS
SORPTION
SORPTIVE PROPERTIES
URANIUM COMPOUNDS
URANYL COMPOUNDS
URANYL NITRATES