Hostname: page-component-78c5997874-j824f Total loading time: 0 Render date: 2024-11-02T23:15:59.240Z Has data issue: false hasContentIssue false
  • English
  • Français

In-Situ Testing of Nuclear Waste Glasses in a Clay Laboratory - Results After Two Years Corrosion

Published online by Cambridge University Press:  21 February 2011

P. Van Iseghem ,
W. Timmermans  and
B. Neerdael
P. Van Iseghem
Affiliation:
Department Nuclear Chemistry and the Fuel Cycle, S.C.K./C.E.N., B-2400 Mol, Belgium
W. Timmermans
Affiliation:
Department Nuclear Chemistry and the Fuel Cycle, S.C.K./C.E.N., B-2400 Mol, Belgium
B. Neerdael
Affiliation:
Department Nuclear Chemistry and the Fuel Cycle, S.C.K./C.E.N., B-2400 Mol, Belgium
Get access

Abstract

The first retrieval of an in-situ experiment on the interaction waste form - clay host in the underground laboratory under the Mol site has been finished successfully. The test consisted in a two years exposure of various candidate simulated waste glasses at 90°C to Boom clay. The retrieval was done by overcoring. The experimental data showed satisfactorily correspondence between in-situ and laboratory simulation tests both for mass loss and surface analytical data, supporting the validity of the in-situ test as it was performed. The thickness of waste form dissolved within two years varies between 40 and 325 μm (case of the high-level waste glasses), depending on the composition. Matrix dissolution is expected to be the major mechanism of interaction.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 176: Symposium U – Scientific Basis for Nuclear Waste Management XIII , 1989 , 283
Copyright
Copyright © Materials Research Society 1990

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. Bonne, A. and Heremans, R., in Radioactive waste management and the nuclear fuel cycle, vol. 6, nrs 3-4, 277 (1985).Google Scholar
2. Hench, L. et al., in Scientific basis for nuclear waste management V, edited by Lutze, W., Elsevier Science Publ.; Mat. Res. Soc. Symp. Proc. vol. 11 (1982), p. 153.Google Scholar
3. Wicks, G. and Molecke, M., in Advances in ceramics, vol. 20, Nuclear Waste Management II, edited by Clark, D.E., White, W.B. and Machiels, A.J., Am. Cer. Soc. Publ., (1988) 657.Google Scholar
4. Casteels, F. et al., in Design and instrumentation of in-situ experiments in underground laboratories for radioactive waste disposal, edited by Côme, B., Johnston, P. and üller, A. M, Balkema, A.A. publ., EUR 9575, (1985) 277.Google Scholar
5. Iseghem, P. Van et al., in Advances in Ceramics, vol. 20, Nuclear waste management II, edited by Clark, D.E., White, W.B. and Machiels, A.J., Am. Cer. Soc. Publ. (1986), 649.Google Scholar
6. Debruyn, W. and Tas, H., in Nuclear & Hazardous Waste Management, Spectrum '88. Am. Nucl. Soc. Publ., Ill, USA (1988) 217.Google Scholar
7. Put, M. et al., in Disposal of Conditioned High-Level and Long-Lived Radioactive Waste in a Deep Clay Formation, Progress Report nr 4 to the CEC for Contracts FI1W-0055-B and FIIW-0145-B.Google Scholar
8. Debruyn, W. et al., Annual Progress Report 1988 to the CEC for Contract FIlW-0033-B.Google Scholar
9. Testing and evaluation of solidified high level radioactive waste, edited by Hall, A.R., Graham & Trotham Publ., EUR 10852 (1987), 173.Google Scholar
10.Characterization of low and medium-level radioactive waste forms, edited by Pottier, P.E. and Glasser, F.P., EUR 10579 (1987), 84.Google Scholar
11. Iseghem, P. Van et al., in Scientific basis for nuclear waste management VII, edited by McVay, G.L., Elsevier Science Publ., Mat. Res. Soc. Symp. Proc. vol. 26 (1984), 527.Google Scholar
12. McVay, G. and Buckwalter, C., PNL-SA-10474 (1982).Google Scholar