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Predicting Pu Concentrations in Solutions Contacting Geologic Materials

Published online by Cambridge University Press:  15 February 2011

Richard G. Strickert  and
Dhanpat Rai
Richard G. Strickert
Affiliation:
Pacific Northwest Laboratory, P.O. Box 999, Richland, Washington 99352
Dhanpat Rai
Affiliation:
Pacific Northwest Laboratory, P.O. Box 999, Richland, Washington 99352
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Abstract

Knowledge of Pu solid phases present in nuclear wastes is important for predicting the geochemical behavior of Pu. Thermodynamic data and experimental measurements using discrete Pu compounds, Pu-doped borosilicate glasses (simulating a high-level waste form), and Pu contaminated sediments suggest that PuO2(c) is very stable and is expected to be present in the repository. The solubility of the stable phase, such as PuO2(c), can be used to predict the maximum Pu concentration in solutions for long-term safety assessment of nuclear waste repositories.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 6: Symposium D – Scientific Basis for Nuclear Waste Management IV , 1981 , 215
Copyright
Copyright © Materials Research Society 1982

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References

REFERENCES

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