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Immobilization and Behavior of Technetium in a Magnesium Titanate Matrix for Final Disposal

Published online by Cambridge University Press:  21 March 2011

Marcel. J. den Exter
Affiliation:
Nuclear Research and Consultancy Group, NRG-FAI, P.O. box 25, 1755 ZG, Petten, The Netherlands
Signe Neumann
Affiliation:
Aachen University of Applied Sciences, Division Jülich, Ginsterweg 1, 52428 Jülich, Germany
Tanja Tomasberger
Affiliation:
Nuclear Research and Consultancy Group, NRG-RE, P.O. box 25, 1755 ZG, Petten, The Netherlands
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Abstract

Technetium was immobilized in a Mg2TiO4 matrix by atomic substitution of titanium for 20, 50 and 80mol%. Leach tests, conforming to the ASTM C-1220-92 specifications, were carried out using simulated leachants (granite water, clay pore water and saturated salt solution) in order to determine normalized leach rates (NL) and fractional releases (FR%).

FR% for technetium have been measured < 0.1% for all Tc-loadings. Typical NL are1.7 E−2 g/m2d and 1.1 E−1 g/m2d for a 50 mol% and 80 mol% Tc-loading. In comparison to published fractional releases for glass, the matrix proves to be a more suitable host.

In addition, inactive pellets were produced and leached for investigation of the behaviour of the matrix material itself and the influence of other phases due to possible incomplete reactions during fabrication. Two types of inactive pellets were produced: Mg2TiO4 and Mg2TiO4/MgTiO3/MgO mixed pellets, the latter by decreasing the temperature during fabrication to 1285°C. Release of titanium from MgTiO3 proves to be higher than for Mg2TiO4.

It was found that the leachability of the host matrix increases upon increasing the technetium loading. As a compromise between waste volume reduction and leachability, it is suggested that technetium loadings do not exceed about 50 mol%.

Type
Research Article
Copyright
Copyright © Materials Research Society 2006

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References

REFERENCES

1. Khalil, M. Y., White, W. B. Magnesium Titanate Spinel: A Ceramic Phase for Immobilisation of Technetium-99 from Radioactive Wastes, Communications of the American Ceramic Society, October 1983, C-197/C-198Google Scholar
2. Gruppelaar, H., Kloosterman, J. L., M, Konings R. J., Advanced Technologies for the Reduction of Nuclear Waste, ECN, ECN-R—98-008, Petten, 1998 Google Scholar
3. Lieser, K. H., Bauscher, Ch., Technetium in the Hydrosphere and in the Geosphere, Radiochimica Acta 42, 1987, pp. 205213 Google Scholar
4. Lieser, K. H., Technetium in the Nuclear Fuel Cycle, in Medicine and in the Environment, Radiochimica Acta 63, 1993, pp. 58 Google Scholar
5. NEA, Actinide and Fission Product Partitioning and Transmutation, Status and Assessment Report, 1999 Google Scholar
6. Clefs No. 46 – Radioactive Waste Management Research, CEA, ISSN 1625-9718, Spring 2002 Google Scholar
7. ASTM Committee C-26, Standard Test Method for Static Leaching of Monolithic Waste Forms for Disposal of Radioactive Waste, Annual Book of ASTM Standards, 1996, Section 12 Nuclear, Solar and Geothermal Energy, Volume 12.01 Nuclear Energy (I)Google Scholar
8. Hart, K.P., Vance, E.R., Day, R.A., Begg, B.D., Angel, P.J. and Jostsons, A., Mat. Res. Soc. Symp. Proc. Vol 412, Editors W, Murphy and Knecht, D., 1996 p 281288 Google Scholar
9. , Cui et al. , Spent Fuel Leaching under Anoxic Conditions and the Effect of Canister Materials, Mat. Res. Soc. Symp. Proc. Vol. 807 – Scientific Basis for Nuclear Waste Management XXVII, Materials Research Society, 2004, pp.8994 Google Scholar
10. Measurement of Concentrations of Matrix Constitutions and Radionuclides Released from Nuclear Waste Forms under Simulated Geological Repository Conditions, EC-Test Procedure, report ENR 12017 EN, CECGoogle Scholar