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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,
J. K. Bates,
J. C. Hoh,
J. W. Emery,
L D. Hafenrichter,
E. C. Buck and
M. Gong
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.

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References

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