Hostname: page-component-78c5997874-8bhkd Total loading time: 0 Render date: 2024-11-10T02:24:52.909Z Has data issue: false hasContentIssue false
  • English
  • Français

Immobilization of HLW in Synroc-E

Published online by Cambridge University Press:  25 February 2011

S.E. Kesson  and
A.E. Ringwood
S.E. Kesson
Affiliation:
Research School of Earth Sciences, Australian National University, G.P.O. Box 4, Canberra, 2601, Australia.
A.E. Ringwood
Affiliation:
Research School of Earth Sciences, Australian National University, G.P.O. Box 4, Canberra, 2601, Australia.
Get access

Abstract

SYNROC-E is a new TiO2- rich formulation designed to immobilize ≤7% HLW. It comprises hollandite, zirconolite, perovskite, pyrochlore and alloy (totalling ˜20%) in a continuous matrix of fully densified rutile, and utilizes the principle of “synthetic rutile microencapsulation” in its microstructure. Short-term (%100 day) tests at 95°C reveal that the leach-rates for Cs,Ca,Sr and Ba lie within about an order of magnitude of one another and fall by %2 orders of magnitude over this time period. Leach-rates for U,Ce,Nd,Ti and Zr are initially extremely low and rapidly fall below ICP detection capabilities. On longer timescales, when SYNROC phases exposed at the surface of the wasteform have been leached away, the very low solubility of the protective rutile matrix should greatly inhibit further leaching. SYNROC-E is particularly suitable for burial in salt or in deep ocean sediments as a consequence of its thermal output, microstructure and its capacity to achieve public acceptability.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 26: Symposium D – Scientific Basis for Nuclear Waste Management VII , 1983 , 507
Copyright
Copyright © Materials Research Society 1984

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

REFERENCES

1. Forberg, S., Westermark, T., Larker, H. and Widell, B., in: Scientific Basis for Nuclear Waste Management, vol. 1, McCarthy, G., ed., Plenum Press, New York, 201–205 (1979).Google Scholar
2. Forberg, S. and Westermark, T., in: Proc. Internat. Seminar on Chemistry and Process Engineering for HLW solidification. Odoj, R. and Merz, E. eds., (Kernforschungsanlage Jülich GmbH) 407–429 (1981).Google Scholar
3. Bauer, C. and Ondracek, G., in: Scientific Basis for Nuclear Waste Management, vol. 4, Brookins, D.C. ed., Elsevier Science, New York, 71–76 (1983).Google Scholar
4. Ringwood, A.E., Kesson, S.E., Ware, N.G., Hibberson, W. and Major, A., Geochem J. 13, 141 (1979).Google Scholar
5. Dosch, R.G. and Lynch, A.W.. Sandia Report SAND80-2375, (1981).Google Scholar
6. Dosch, R.G., Headley, T.J., Northrup, C.J. and Illava, P.F.. Sandia Report SAND82–2980 (1983).Google Scholar
7. Saum, C.J., Ford, L.H. and Blatts, N., in: Proc. Internat. Seminar on Chemistry and Process Engineering for HLW solidification. Odoj, R. and Merz, E. eds., Kernforschungsanlage Jülich, GmbH, 277–302 (1981).Google Scholar
8. Kennedy, J., Peckett, J.W. and Perkins, R.. U.K. AEA Report AERE – R 4516 (1964).Google Scholar
9. Ringwood, A.E., Oversby, V.M., Kesson, S.E., Sinclair, W., Ware, N., Hibberson, W. and Major, A., Nucl. Chem. Waste Manag. 2, 287 (1981).Google Scholar
10. Ringwood, A.E., Major, A., Ramm, E.J. and Padgett, J.. Nucl. Chem. Waste Manag. in press (1983).Google Scholar
11. Kesson, S.E., Rad. Waste Manag. and the Nucl. Fuel Cycle, in press, (1983).Google Scholar
12. Ryerson, F.J., Hoenig, C.L. and Smith, G.S., Lawrence Livermore Lab. UCRL- 86880 (1981).Google Scholar
13. Oversby, V.M. and Ringwood, A.E.. Rad. Waste Manag. and the Nucl. Fuel Cycle 2, 223 (1982).Google Scholar