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Dissolution of UO2 at Various Parametric Conditions: A Comparison Between Calculated and Experimental Results

Published online by Cambridge University Press:  26 February 2011

Kaija Olliia
Kaija Olliia*
Affiliation:
Technical Research Centre of Finland, Reactor Laboratory, Otakaari 3 A, SF-02150 Espoo, Finland
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Abstract

The solubilities of uranium measured in deionized water, in sodium bicarbonate solutions as a function of carbonate concentration and in two types of synthetic groundwaters have been compared with those predicted using the reaction pathway program, PHREEQE. All the measurements were carried out under both air-saturated, oxidizing and anoxic, reducing conditions.

The experimental solubility values of uranium under oxidizing conditions are, in general, lower when compared to the corresponding theoretical ones calculated by PHREEQE. A critical factor is the choice of solubility constant for the solid phase. The reason for the lower solubility values may also be the mechanism of dissolution leading for example either to a situation where low dissolution rate is a limiting factor, or to formation of some solid phase of uranium with lower solubility. The experimental solubility values under reducing conditions appear to be in good agreement with the theoretical solubility values.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 127: Symposium BERLIN – Scientific Basis for Nuclear Waste Management XII , 1988 , 337
Copyright
Copyright © Materials Research Society 1989

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References

REFERENCES

[1] Cross, J.E., Ewart, F.T. and Tweed, C.J., Thermochemical modelling with application to nuclear waste processing and disposal, AERE-R 12324 Harwell Laboratory, Harwell, England (1987).Google Scholar
[2] Allard, B., Larsen, S.A., Albinsson, Y., Tullborg, E.L., Karlsson, M., Andersson, K. and Torstenfeit, B., in Near-Field Phenomena in Geologic Repositories for Radioactive Waste, (Nuclear Energy Agency, Paris, 1981), pp. 93–101.Google Scholar
[3] Snellman, M., in Third Finnish-German Seminar on Nuclear Waste Management 1986, edited by Lamberg, L., (Technical Research Centre of Finland, Espoo, 1988), pp. 146–168.Google Scholar
[4] Ollila, K., Dissolution mechanicm of UO2 at various parametric conditions, Report YOT-88–04, Technical Research Centre of Finland, Espoo (1988).Google Scholar
[5] Wang, R., Katayama, Y.B., Nuclear and Chemical Waste Management, 3, 83(1982).Google Scholar
[6] Shoesmith, D.W., Sunder, S., Bailey, M.G. and Wallace, G.J., in Second Internat. Conf. on Radioactive Waste Management, (Canadian Nuclear Society, Toronto, 1986), pp. 674–679.Google Scholar
[7] Strays-Gascoyne, S., Johnson, L.H., Beeley, P.A. and Sellinger, D.M., in Scientific Basis for Nuclear Waste Management IX, edited by Werme, L. (Materials Research Society, Pittsburgh, 1986), pp. 317–326.Google Scholar
[8] Forsyth, R.S., Werme, L.O., Bruno, J., Journal of Nuclear Material 138, 1(1986).Google Scholar
[9] Garisto, F., Garisto, N.C., Nuclear and Chemical Waste Management 6, 203(1986).Google Scholar
[10] Bruno, J., Casas, I. and Puigdomenech, I., presented at Internat. Conf. on Chemistry and Migration Behaviour of Actinides and Fission Products in the Geosphere, Munich, 1987, (Proceedings to be published in Radio-chimica Acta)Google Scholar
[11] Forsyth, R.S., Werme, L.O., Corrosion tests on spent PWR fuel in synthetic groundwater, KBS Technical Report 87–16, Stockholm, Sweden (1987).Google Scholar