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Plutonium Leaching from a Reference Nuclear Waste Glass in Synthetic Interstitial Claywater

Published online by Cambridge University Press:  01 January 1992

Lian Wang
Affiliation:
S.C.K./C.E.N, Boeretang 200, 2400 Mal, Belgium
P. Van Iseghem
Affiliation:
S.C.K./C.E.N, Boeretang 200, 2400 Mal, Belgium
A. Maes
Affiliation:
Laboratorium voor Colloidale Schelkunde, Kardinaal Mercierlaan 92, 3001 Leuven, Belgium
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Abstract

The steady-state concentration of Pu was measured upon leaching Pu doped glass in synthetic interstitial claywater (SIC) and humic acid free interstitial solution (IS). The solubility of PuO2·xH2O(am) was determined in the same chemical condition. The results then were compared with the Pu solubility calculated by using a published solubility product and complex stability constants. The humic acid (HA) influence on the Pu leaching from the glass and the colloid formation were investigated.

Type
Research Article
Copyright
Copyright © Materials Research Society 1993

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References

REFERENCES

[1] Marivoet, J. and Bonne, A., PAGIS, Performance Assessment of Geological Isolation Systems for Radioactive Waste: Disposal in Clay Formations. EUR 11776 (1988).Google Scholar
[2] Van Iseghem, P., Berghman, K., Lemmens, K., Timmermans, W., Wang, Lian, Laboratory and in-situ interaction between simulated waste glasses and clay. Final report, EUR 13607EN (1992)Google Scholar
[3] Rai, D. and Ryan, J. L., Solubility constraints: An important consideration in safety assessment of nuclear waste disposal. In Scientific Basis for Nuclear Waste Management VII, pp. 105285. (1984)Google Scholar
[4] Kim, J.I. and, Kanellakopulos, B., Solubility products of plutonium (IV) oxide and hydroxide. Radiochimica. Acta. 48, 145-150 (1989).Google Scholar
[5] Rai, D., Solubility product of Pu(IV) hydrous oxide and equilibrium constants of Pu(IV)/Pu(V), Pu(IV)/Pu(VI) and Pu(V)/Pu(VI) couples. Ridiochimica Acta 35, 97-106 (1984).Google Scholar
[6] Skytte Jensen, B., The geochemistry of radionuclides with long halflives, their expected migration behaviour. Risϕ-R-430, Risϕ National Laboratory, DK-4000 Roskilde, Denmark. November 1980.Google Scholar
[7] Nitsche, H., Basic research for assessment of geologic nuclear waste repositories: What solubility and speciation studies of transuranium elements can tell us. Mat. Res. Soc. Symp. Proc. Vol. 212. pp 517 (1991).Google Scholar
[8] Maes, A., De Brabandere, J. and Cremers, A., Complexation of Eu3+ and Am3+ with Humic Substances. Radiochimica Acta 52/53, 41-47 (1991).Google Scholar
[9] Means, J. L., The importance of organic compounds in ground water as radionuclide mobilizing agents, Battlle Columbus Laboratories, ONWI-348, pp.28 (1982).Google Scholar
[10] Bondietti, E. A., Reynolds, S. A. and Shanks, M. H., interaction of plutonium with complexing substances in soils and natural waters, in Transuranic Nuclide in the Environment, International Atomic Energy Agency, IAEA-SM-199/51, pp.273-287 (1975).Google Scholar