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Pretreatment of Tc-Containing Waste and Its Effect on Tc-99 Leaching from Grouts

Published online by Cambridge University Press:  19 October 2011

Albert Aloy ,
Elena N Kovarskaya ,
John R. Harbour ,
Christine A. Langton  and
E William Holtzscheiter
Albert Aloy
Affiliation:
[email protected], "V.G. Khlopin Radium Institute" (KRI), RosAtom, 2-nd Murinsky str., 28, Saint Petersburg, 194021, Russian Federation, +7 812 545 42 15, +7 812 545 42 15
Elena N Kovarskaya
Affiliation:
[email protected], "V.G. Khlopin Radium Institute" (KRI), RosAtom, 2-nd Murinsky str., 28, Saint Petersburg, 194021, Russian Federation
John R. Harbour
Affiliation:
[email protected], Savannah River National Laboratory, Washington Savannah River Company, Savannah River National Laboratory, Aiken, SC, 29808, United States
Christine A. Langton
Affiliation:
[email protected], Savannah River National Laboratory, Washington Savannah River Company, Savannah River National Laboratory, Aiken, SC, 29808, United States
E William Holtzscheiter
Affiliation:
[email protected], Savannah River National Laboratory, Washington Savannah River Company, Savannah River National Laboratory, Aiken, SC, 29808, United States
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Abstract

A salt solution (doped with Tc-99), that simulates the salt waste stream to be processed at the Saltstone Production Facility, was immobilized in grout waste forms with and without (1) ground granulated blast furnace slag and (2) pretreatment with iron salts. The degree of immobilization of Tc-99 was measured through monolithic and crushed grout leaching tests. Although Fe (+2) was shown to be effective in reducing Tc-99 to the +4 state, the strong reducing nature of the blast furnace slag present in the grout formulation dominated the reduction of Tc-99 in the cured grouts. An effective diffusion coefficient of 4.75 x 10-12 (Leach Index of 11.4) was measured using the ANSI/ANS-16.1 protocol. The leaching results show that, even in the presence of a concentrated salt solution, blast furnace slag can effectively reduce pertechnetate to the immobile +4 oxidation state. The measured diffusivity was introduced into a flow and transport model (PORFLOW) to calculate the release of Tc-99 from a Saltstone Vault as a function of hydraulic conductivity of the matrix.

Keywords

waste managementdiffusionabsorption
Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 985: Symposium NN – Scientific Basis for Nuclear Waste Management XXX , 2006 , 0985-NN10-02
Copyright
Copyright © Materials Research Society 2007

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References

REFERENCES

1. Harbour, J. R., Edwards, T. B., Lorier, T. H., Langton, C. A., Moore, R. C., Krumhansl, J. L., Holt, K. C., Salas, F., and Sanchez, C. A., WSRC-TR-2004-00021, Rev.0. (2004).Google Scholar
2. Lieser, K. H., Bauscher, Ch., Radiochemical Acta, 42, 205–213 (1987).Google Scholar
3. Mashkin, A. N., Shikov, S. L., Radiation Safety Issues J., Ozyorsk, Mayak, Russia, No.1, pp. 12–17 (1999).Google Scholar
4. Rapp, A. F.. Proceedings of the International Conference on a Peaceful Use of Atomic Energy. Geneva, 1955, Fizmatiz, 14, pp.86–103 (1958).Google Scholar
5. Mashkin, A. N., Kobelev, A. V., Radiation Safety Issues J., Ozyorsk, Mayak, Russia, 36–41 (2000).Google Scholar
6. Momoshima, N., Sayad, M., Yamada, M., Takamura, M., Kawamura, H., J. of Radioanalytical and Nuclear Chemistry, 266, No.3,.455–461 (2005).Google Scholar
7. Shuh, D. K., Project Number: EMSP-73778. Final report, p.34, DOE, U.S, (2003).Google Scholar
8. ASTM D-5233, Standard Test Method for Single Batch Extraction Method for Waste Distribution, ASTM, Philadelphia, PA 19103 (1999).Google Scholar
9. American National Standard ANSI/ANS-16.1, Measurement of the Leachability of Solidified Low-Level Radioactive Wastes by a Short-Term Test Procedure (1986).Google Scholar