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Immobilization of Cs-137, Co-60, Mn-54 And Sr-85 in Cement-Waste Composition

Published online by Cambridge University Press:  26 February 2011

I. Plećaš ,
J. Drljača ,
A. Perić  and
A. Kostadinović
I. Plećaš
Affiliation:
“Boris Kidrič”Institute of Nuclear Sciences-Vinča P.O. Box 522, 11001 Belgrade, Yugoslavia
J. Drljača
Affiliation:
“Boris Kidrič”Institute of Nuclear Sciences-Vinča P.O. Box 522, 11001 Belgrade, Yugoslavia
A. Perić
Affiliation:
“Boris Kidrič”Institute of Nuclear Sciences-Vinča P.O. Box 522, 11001 Belgrade, Yugoslavia
A. Kostadinović
Affiliation:
“Boris Kidrič”Institute of Nuclear Sciences-Vinča P.O. Box 522, 11001 Belgrade, Yugoslavia
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Abstract

To assess the safety for disposal of radioactive waste cement composite, the leaching of Cs-137, Co-60, Mn-54 and Sr-85 from a waste composite into a surounding fluid has been studied [1, 2]. Leaching tests were carried out in accordance with a method recommended by IAEA |2, 3|. Determination of retardation factors, KF, and coefficients of distribution, kd, using a simplified mathematical model for analysing the migration of radionuclides, has been developed. |4, 7, 8|

Results presented in this paper are examples of results obtained in a 10 year mortar and concrete testing project, which will influence the design of the engineered trenche system for future central Yugoslavian radioactive waste storage center. |7, 8|.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 127: Symposium BERLIN – Scientific Basis for Nuclear Waste Management XII , 1988 , 501
Copyright
Copyright © Materials Research Society 1989

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References

REFERENCES

1. Hashimoto, I., IEC Fundamentals 3, 213 (1964)CrossRefGoogle Scholar
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7. Plećaš, I., Proc. Waste Management, Tucson, Arizona, 2, 1861 (1983)Google Scholar
8. Plećaš, I., RWMADW, 6(2), 161 (1985).Google Scholar