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Effects of the Environmental Pressure in the Corrosion Potential of the Copper that Will Be Used as Container of High Level Radioactive Waste

Published online by Cambridge University Press:  01 February 2011

I. Escobar ,
E Silva ,
C. Lamas ,
C. Silva  and
L. Werme
I. Escobar
Affiliation:
Comisión Chilena de Energía Nuclear (CCHEN), Amunátegui 95, Santiago, Chile
E Silva
Affiliation:
Comisión Chilena de Energía Nuclear (CCHEN), Amunátegui 95, Santiago, Chile
C. Lamas
Affiliation:
Comisión Chilena de Energía Nuclear (CCHEN), Amunátegui 95, Santiago, Chile
C. Silva
Affiliation:
Comisión Chilena de Energía Nuclear (CCHEN), Amunátegui 95, Santiago, Chile
L. Werme
Affiliation:
Svensk Kärnbränslehantering AB (SKB), Brahegatan 47, Stockholm, Sweden
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Abstract

The SKB project of Sweden has considered copper as the most appropriate metal to be used as container for high activity radioactive waste. However, it is still necessary to carry out some studies that can assure that their chemical, physical, mechanical properties, etc. do not loose stability in a period so long as 100.000 years.

In this work we show using anodic polarization, the corrosion potential (Ecorr) behaviour in different pressurized environment. The copper surface was characterized using optical microscopy. The electrochemical cell was mounted in a high pressure chamber that allowed to work up to 40 atm. The electrolyte solution simulates the deep groundwater, being the composition reported in literature [1].

The experimental results in solutions without bentonite show only slightly changes of the corrosion potential to cathodic values. At pressures of 40 atm, products of corrosion are observed, covering micropitting, that can be induced because of a bigger interaction metal/ ion at these pressures.

In the other case, bentonite presence produces beneficial effects in the resistance of the copper corrosion, since it is observed that the corrosion potential is displaced to more anodics values. This effects could be explained due to that this clay is able to retain ions that are aggressives for copper, such as chloride, sulphide, etc., and it liberates others that don't produce deterioration, such as sodium, that is in concordance with others authors[15].

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 807: Symposium Scientific Basis for Nuclear Waste Management XXVII , 2003 , 453
Copyright
Copyright © Materials Research Society 2004

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References

REFERENCES

1. RD&D-PROGRAMME 95, Treatment and Final Disposal of Nuclear Waste‥ Svensk Kärnbränslehantering AB (SKB). September 1995, pp 79–80.Google Scholar
2. Wersin, P., Spahiu, K., Bruno, J. Swedish Nuclear Fuel and Waste Management Co. Stockholm. Septembre 1994. Technical Report 94–25.Google Scholar
3. Beverskog, B., Puigdomenech, I. J. Electrochem. Soc, Vol. 144, N° 10, October 1997, pp 3476–3483.Google Scholar
4. Puigdomenech, I., Taxén, C. Stockholm. January 2000, Technical Report TR-2000–13.Google Scholar
5. Pedersen, K. Swedish Nuclear Fuel and Waste Management Co. Stockholm. April 2000. Technical Report 2000–04.Google Scholar
6. Imai, H, Fukuda, T., Akashi, M. Material Research Society Proceeding. Vol 412, 1996, pp 589–596 Google Scholar
7. Ahonen, L. December 1995. Nuclear Waste Commission of Finnish Power Companies. Report YJT-95–19Google Scholar
8. Drogowska, M., Brossard, L., Ménard, H., Lasia, A. Surface and Coatings Technology, 34 (1988), pp. 404–416.Google Scholar
9. Pérez Sánchez, M., Barrera, M., González, S., Souro, R.M., Salvarezza, R.C., Arvia, A.J. Electrochimica Acta. Vol. 35, N° 9, pp. 1337–1343, 1990. Gran Bretaña.Google Scholar
10. Sridhar, N., Cragnolino, G.A. Corrosion Science, vol. 49, N° 12, pp. 967–977.Google Scholar
11. Nilson, F. Swedish Nuclear Fuel and Waste Management Co. Stockholm. December 1992. Technical Report 92–45.Google Scholar
12. Pettersson, K., Oskarsson, M. Material Research Center. The Royal Institute of Technology. Stockholm, July 1997. TRITA-MAC-0611.Google Scholar
13. King, F., Litke, C.D., Ikeda, B.M. Corrosion 99. Paper N° 482, pp. 1–31.Google Scholar
14. Maiya, P.S., Shack, W.J., Kassner, T.F. Corrosion, vol. 46, N° 12, Decembre 1990, pp. 954–963.Google Scholar
15. Push, R.; Jacobsson, A. Symposium on the underground disposal of radioactive waste. Otaniemi, Finland, 2 July 1979. Proceeding serie v1, pp 487–501. IAEA – SM – 243/22 (IAEA ASM24322).Google Scholar