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Development and Characterization of Borosilicate Glasses for Immobilization of Plutonium-containing Alkaline Sludges

Published online by Cambridge University Press:  21 March 2011

A.S. Aloy ,
O.A. Iskhakova ,
T.I. Koltsova ,
A.V. Trofimenko  and
L.J. Jardine
A.S. Aloy
Affiliation:
RPA (V.G. Khlopin Radium Institute), St. Petersburg, Russian Federation
O.A. Iskhakova
Affiliation:
RPA (V.G. Khlopin Radium Institute), St. Petersburg, Russian Federation
T.I. Koltsova
Affiliation:
RPA (V.G. Khlopin Radium Institute), St. Petersburg, Russian Federation
A.V. Trofimenko
Affiliation:
RPA (V.G. Khlopin Radium Institute), St. Petersburg, Russian Federation
L.J. Jardine
Affiliation:
University of California, Lawrence Livermore National Laboratory, USA
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Abstract

Several glasses were melted using laboratory-scale microwave (MW) equipment to study the vitrification of Pu-containing sludges from the Mining and Chemical Combine in Zheleznogorsk, Russia. This work is part of an effort to identify glass compositions that can be adopted for industrial scale production. The glass must meet durability requirements and have good technological properties for long-term storage and geologic disposal.

Electron Probe Analysis (EMPA), scanning electron microscope (SEM) and x-ray methods were used to characterize glasses containing 50 wt% solid sludge residues with high sodium content.

Leach tests of 3, 7, 14, and 28 day durations were performed using the MCC-1 method at 90°C. The surface of the glass was analyzed before and after leaching. Based on the observed results, there are differences in the behavior of Pu and U for the glasses tested, and glass durability is dependent on homogeneity, the uranium oxidizing state, and the SiO2/Na2O+Li2O ratio.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 663: Symposium – Scientific Basis for Nuclear Waste management XXIV , 2000 , 189
Copyright
Copyright © Materials Research Society 2001

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References

REFERENCES

1. Jardine, L. J., Revenko, Y.A., Kudinov, K.G., et al., Technical and Engineering Feasibility Study of the Vitrification of Plutonium-Bearing Sludges at the Krasnoyarsk Mining and Chemical Combine by Means of Microwave Heating, Lawrence Livermore National Laboratory, UCRL–JC–136383, American Nuclear Society Topical Meeting, DOE Spent Fuel and Fissile Materials Management, June 4–8, San Diego, CA Preprint, March 3, 2000.Google Scholar
2. Aloy, A.S., Belov, V.Z., Iskhakova, O.A., Trofimenko, A.V., “Characterization of Borosilicate Composition Developed for the Immobilization of Plutonium-containing Sludges at MCC”, A Review of LLNL Contract Work. Proceedings of the Meeting for Coordination and Review of Work Held in St. Petersburg, Russia, Lawrence Livermore National Laboratory, UCRL–ID–138361, November 1-4, pp. 153–166, 1999.Google Scholar
3. Petersen, R. D., “Microwave Vitrification Of Rocky Flats TRU Sludge”, Spectrum 90, Oak Ridge, Tennessee, October 1990, RFP–4414.Google Scholar
4.Technical Report Series # 383, Characterization of Radioactive Waste Forms and Packages, IAEA, Vienna, 1997.Google Scholar
5. Karraker, D. G., “Actinide valences in borosilicate glass”, J. Amer. Ceram. Soc., 65 (1), pp. 53–55, 1982.Google Scholar