Dissolution characteristics of mixed UO{sub 2} powders in J-13 water under saturated conditions
The Yucca Mountain Project/Spent Fuel program at Argonne National Laboratory is designed to determine radionuclide release rates by exposing high-level waste to repository-relevant groundwater. To gain experience for the tests with spent fuel, a scoping experiment was conducted at room temperature to determine the uranium release rate from an unirradiated UO{sub 2} powder mixture (14.3 wt % enrichment in {sup 235}U) to J-13 water under saturated conditions. Another goal set for the experiment was to develop a method for utilizing isotope dilution techniques to determine whether the dissolution rate of UO{sub 2} matrix is in accordance with an existing kinetic model. Results of these analyses revealed unequal uranium dissolution rates from the enriched and depleted portions of the powder mixture because of undisclosed differences between them. Although the presence of this inhomogeneity has precluded the application of the kinetic model, it also provided an opportunity to elaborate on the utilization of isotope dilution data in recognizing and quantifying such conditions. Detailed listings of uranium release and solution chemistry data are presented. Other problems commonly associated with spent fuel, such as the effectiveness of filtering media, the existence of uranium concentration peaks during early stages of the leach tests, the need for concentration corrections due to water replenishments of sample volumes, and experience derived from isotope dilution data are discussed in the context of the present results. 10 refs., 5 figs., 7 tabs.
- Research Organization:
- Argonne National Lab., IL (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 138082
- Report Number(s):
- ANL--91/8; ON: DE91010968
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
05 NUCLEAR FUELS
54 ENVIRONMENTAL SCIENCES
ANL
CONTAINERS
DISSOLUTION
ENCAPSULATION
GROUND WATER
HIGH-LEVEL RADIOACTIVE WASTES
IMPURITIES
LAWRENCE LIVERMORE LABORATORY
LEACHING
OXIDATION
POWDERS
QUANTITY RATIO
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTE MANAGEMENT
RADIONUCLIDE MIGRATION
REACTION KINETICS
RESEARCH PROGRAMS
SCHOEPITE
SITE CHARACTERIZATION
SPENT FUELS
URANIUM
URANIUM DIOXIDE
WATER CHEMISTRY
YUCCA MOUNTAIN
Yucca Mountain Project
54 ENVIRONMENTAL SCIENCES
ANL
CONTAINERS
DISSOLUTION
ENCAPSULATION
GROUND WATER
HIGH-LEVEL RADIOACTIVE WASTES
IMPURITIES
LAWRENCE LIVERMORE LABORATORY
LEACHING
OXIDATION
POWDERS
QUANTITY RATIO
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTE MANAGEMENT
RADIONUCLIDE MIGRATION
REACTION KINETICS
RESEARCH PROGRAMS
SCHOEPITE
SITE CHARACTERIZATION
SPENT FUELS
URANIUM
URANIUM DIOXIDE
WATER CHEMISTRY
YUCCA MOUNTAIN
Yucca Mountain Project