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Leach Resistance Properties and Release Processes for Salt-Occluded Zeolite A

Published online by Cambridge University Press:  01 January 1992

M. A. Lewis ,
D. F. Fischer  and
J. J. Laidler
M. A. Lewis
Affiliation:
Argonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439
D. F. Fischer
Affiliation:
Argonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439
J. J. Laidler
Affiliation:
Argonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439
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Abstract

The pyrometallurgical processing of spent fuel from the Integral Fast Reactor (IFR) results in a waste of LiCI-KCI-NaCI salt containing approximately 10 wt% fission products, primarily CsCI and SrCI2. For disposal, this waste must be immobilized in a form that it is leach resistant. A salt-occluded zeolite has been identified as a potential waste form for the salt. Its leach resistance properties were investigated using powdered samples. The results were that strontium was not released and cesium had a low release, 0.056 g/m2 for the 56 day leach test. The initial release (within 7 days) of alkali metal cations was rapid and subsequent releases were much smaller. The releases of aluminum and silicon were 0.036 and 0.028 g/m2, respectively, and were constant. Neither alkali metal cation hydrolysis nor exchange between cations in the leachate and those in the zeolite was significant. Only sodium release followed t0.5 kinetics. Selected dissolution of the occluded salt was the primary release process. These results confirm that salt-occluded zeolite has promise as the waste form for IFR pyroprocess salt.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 294: Symposium V – Scientific Basis for Nuclear Waste Management XVI , 1992 , 95
Copyright
Copyright © Materials Research Society 1993

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References

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