Hostname: page-component-586b7cd67f-tf8b9 Total loading time: 0 Render date: 2024-11-24T17:56:40.744Z Has data issue: false hasContentIssue false
  • English
  • Français

Crystallisation Within Simulated High Level Waste Borosilicate Glass

Published online by Cambridge University Press:  17 March 2011

Peter B. Rose ,
Michael I. Ojovan ,
Neil C. Hyatt  and
William E. Lee
Peter B. Rose
Affiliation:
Immobilisation Science Laboratory, Department of Engineering Materials, University of Sheffield, Mappin Street, Sheffield, S1 3JD, U.K, [email protected]
Michael I. Ojovan
Affiliation:
Immobilisation Science Laboratory, Department of Engineering Materials, University of Sheffield, Mappin Street, Sheffield, S1 3JD, U.K, [email protected]
Neil C. Hyatt
Affiliation:
Immobilisation Science Laboratory, Department of Engineering Materials, University of Sheffield, Mappin Street, Sheffield, S1 3JD, U.K, [email protected]
William E. Lee
Affiliation:
Immobilisation Science Laboratory, Department of Engineering Materials, University of Sheffield, Mappin Street, Sheffield, S1 3JD, U.K, [email protected]
Get access

Abstract

The devitrification products of two simulated high level radioactive waste (HLW) glasses have been investigated. Magnox waste glass contained RuO2 as its primary crystal phase, Pd-Te inclusions, a Cr-, Fe- and Ni-rich spinel phase, a Si- and lanthanide-rich phase and also a Zr-rich phase which incorporated Ce and Gd. Upon heat treatment the glass developed a zektzerite-type phase, CeO2, a strontium molybdate (containing Nd and La) as well as a Si-rich phase. 75/25 glass, comprising a blend of reprocessing waste derived from UO2 and Magnox fuels, contained RuO2 as its primary crystalline phase, CeO2 and a Si- and Ru-rich phase. Heat treatment of this glass resulted in the growth of the CeO2 crystals, the development of a strontium molybdate (containing Nd and La) and a Si- and lanthanide-containing phase. A sodium lanthanum molybdate with a powellite-type structure formed on the surface of both glasses after heat treatment in air.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 824: Symposium CC – Scientific Basis for Nuclear Waste Management XXVIII , 2004 , CC5.6
Copyright
Copyright © Materials Research Society 2004

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

1. Lutze, W., Silicate Glasses in Radioactive Wasteforms for the Future, ed. Lutze, W. and Ewing, R. C. (Elsevier, 1988) pp. 1–192.Google Scholar
2. Kelm, M. and Oser, B., Mat. Res. Soc. Symp. Proc. 257, 177–183 (1992).Google Scholar
3. Pacaud, F., Fillet, C. and Jacquet-Francillion, N., Mat. Res. Soc. Symp. Proc. 257, 161–167 (1992).Google Scholar
4. Buechele, A. C., Fang, X., Gu, H. and Pegg, I. L., Mat. Res. Soc. Symp. Proc. 176, 393–402 (1990).Google Scholar
5. Kawamura, K. and Ohuchi, J., Mat. Res. Soc. Symp. Proc. 353, 87–93 (1995).Google Scholar
6. Jacquet-Francillion, N., Pacaud, F. and Queille, P., Mat. Res. Soc. Symp. Proc. 11, 249–259 (1982).Google Scholar
7. Short, R. J., Hand, R. J. and Hyatt, N. C., Mat. Res. Soc. Symp. Proc. 757, 141–146 (2003).Google Scholar