Hostname: page-component-586b7cd67f-t8hqh Total loading time: 0 Render date: 2024-11-29T07:27:45.842Z Has data issue: false hasContentIssue false

The Development and Testing of Synroc C as a High Level Nuclear Waste Form

Published online by Cambridge University Press:  15 February 2011

K.D. Reeve
Affiliation:
Australian Atomic Energy Commission Research Establishment, Sutherland NSW 2232Australia
D.M. Levins
Affiliation:
Australian Atomic Energy Commission Research Establishment, Sutherland NSW 2232Australia
E.J. Ramm
Affiliation:
Australian Atomic Energy Commission Research Establishment, Sutherland NSW 2232Australia
J.L. Woolfrey
Affiliation:
Australian Atomic Energy Commission Research Establishment, Sutherland NSW 2232Australia
W.J. Buykx
Affiliation:
Australian Atomic Energy Commission Research Establishment, Sutherland NSW 2232Australia
Get access

Abstract

The current status of SYNROC C research and development by the Australian Atomic Energy Commission is reviewed. A non-radioactive fabrication demonstration line designed to produce 10 cm o.d., 90 cm long, cylinders of SYNROC canned in stainless steel by the method of in-can hot pressing is being commissioned. Leach tests are proving the excellent leach resistance of SYNROC. Accelerated radiation damage testing using fast neutrons has simulated storage times of up to 6.7×105 years. Thermophysical properties of SYNROC have been measured over the temperature range 20–650°C.

Type
Research Article
Copyright
Copyright © Materials Research Society 1982

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. Ringwood, A.E. et al. , Geochem. J. (Japan) 13, 141 (1979).Google Scholar
2. Reeve, K.D. et al. , Proc. Waste Management '81 (Tucson, Arizona, 23–26 February 1981) pp. 249266.Google Scholar
3. Ramm, E.J. and Ringwood, A.E., Australian Patent Application No. 72825–81 (1981).Google Scholar
4. Dosch, R.G. and Lynch, A.W., SAND 80–2375 (1980).Google Scholar
5. Haegi, W. et al. , Energie Nucleaire 10, 152 (1968).Google Scholar
6. Ringwood, A.E. et al. , Nucl. & Chem. Waste Management (in press).Google Scholar
7. International Organization for Standardization (ISO), Draft International Standard DIS/6961 (Berlin 1979).Google Scholar
8. Materials Characterization Center, Draft MCC–1 Static Leach Test (Pacific Northwest Laboratory, Jan. 1981)Google Scholar
9. Coles, D.G. and Bazan, F., J. of Nuclear Technology, in press.Google Scholar
10. Reeve, K.D. and Woolfrey, J.L., J. Aust. Ceram. Soc. 16, 10 (1980).Google Scholar
11. Parker, W.J. et al. , J. Appl. Phys. 32, 1679 (1961).Google Scholar
12. Takahashi, Y., J. Nucl. Mat. 51, 17 (1974).Google Scholar
13. Hoenig, C.L. et al. , UCRL–53143 (1981).Google Scholar
14. Mendel, J.E. et al. , BNWL–2252 (1977).Google Scholar