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Elements Present in Leach Solutions from Unsaturated Spent Fuel Tests

Published online by Cambridge University Press:  25 February 2011

P. A. Finn
Affiliation:
Argonne National Laboratory, Chemical Technology Division, 9700 S. Cass Avenue, Argonne, IL 60439.
J. K. Bates
Affiliation:
Argonne National Laboratory, Chemical Technology Division, 9700 S. Cass Avenue, Argonne, IL 60439.
J. C. Hoh
Affiliation:
Argonne National Laboratory, Chemical Technology Division, 9700 S. Cass Avenue, Argonne, IL 60439.
J. W. Emery
Affiliation:
Argonne National Laboratory, Chemical Technology Division, 9700 S. Cass Avenue, Argonne, IL 60439.
L D. Hafenrichter
Affiliation:
Argonne National Laboratory, Chemical Technology Division, 9700 S. Cass Avenue, Argonne, IL 60439.
E. C. Buck
Affiliation:
Argonne National Laboratory, Chemical Technology Division, 9700 S. Cass Avenue, Argonne, IL 60439.
M. Gong
Affiliation:
Argonne National Laboratory, Chemical Technology Division, 9700 S. Cass Avenue, Argonne, IL 60439.
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Abstract

Preliminary results for the composition of the leachate from unsaturated tests at 90°C with spent fuel for two successive periods of ~60 days each with pretreated J-13 groundwater are reported. The pH of the leachate solutions ranged from 4 to 7. The americium concentration was 104 to 105 greater than that reported for saturated spent fuel tests in which the leachate pH was 8. The major fraction of material in the leachate was present as colloids containing both americium and curium. The presence of actinides in a form not currently directly included in repository radionuclide transport models provides information that can be used in spent fuel reaction modeling, the performance assessment of the repository and the design of the engineering barrier system.

Type
Articles
Copyright
Copyright © Materials Research Society 1994

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References

REFERENCES

1 Wilson, C. N., Results from NNWSI Series 3 Spent Fuel Dissolution Tests, Pacific Northwest Laboratory Report PNL-7170 (1990), and references therein.Google Scholar
2 Nguyen, S. N., Weed, H. C., Leider, H. R., and Stout, R. B., Dissolution Kinetics of UO2-Flow-through Tests on UO2.00 Pellets and Polycrvstalline Schoepite Samples in Oxygenated. Carbonate/Bicarbonate Buffer Solutions at 25°C, Lawrence Livermore National Laboratory Report, UCRL-JC-107478 (1991).CrossRefGoogle Scholar
3 Wilson, C. N. and Gray, W. J., “The Effects of Water Composition on the Dissolution Rate of UO2 Under Oxidizing Conditions,” 1st Internat. High-Level Radioactive Waste Mgmt. Conf., Las Vegas, April 1990.Google Scholar
4 Bates, J. K. and Gerding, T. J., One-Year Results of the NNWSI Unsaturated Test Procedure: SRL 165 Glass Application, Argonne National Laboratory Report ANL-85-41 (1986).Google Scholar
5 Wasywich, K. M. and Frost, C. R., Behavior of Used CANDU Fuel Stored in 150°C Moisture-Saturated Air, 3rd Internat. High-Level Radioactive Waste Mgmt. Conf., Las Vegas, April 1992.Google Scholar
6 Glassley, W. E., Reference Waste Package Environment Report, Lawrence Livermore National Laboratory Report UCRL-53726 (1986).CrossRefGoogle Scholar
7 Guenther, R. J. et al. , Characterization of Spent Fuel Approved Testing Material -ATM-103, Pacific Northwest Laboratory Report PNL-5109-103 (1988).CrossRefGoogle Scholar
8 Guenther, R. J. et al. , Characterization of Spent Fuel Approved Testing Material -ATM-106, Pacific Northwest Laboratory Report PNL-5109-106 (1988).CrossRefGoogle Scholar
9 Kerrisk, J. F. and Silva, R. J., “A Consistent Set of Thermodynamic Constants for Americium(III) Species with Hydroxyl and Carbonate,” Proc. Workshop on Geochemical Modeling, CONF-8609134, pp. 167–175 (1986).CrossRefGoogle Scholar
10 Bates, J. K. et al. . ANL Technical Support Program for DOE Environmental Restoration and Waste Management. Annual Report. October 1991-September 1992, Argonne National Laboratory Report ANL-93/13 (1993).CrossRefGoogle Scholar