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Preparation of Hydrated Glass as a Model of Long-Term Leached Nuclear Waste Glass

Published online by Cambridge University Press:  15 February 2011

Hiroshi Yamanaka
Affiliation:
Osaka National Research Institute, 1-8-31 Midorigaoka, Ikeda, Osaka 563, Japan
Junji Nishii
Affiliation:
Osaka National Research Institute, 1-8-31 Midorigaoka, Ikeda, Osaka 563, Japan
Tomoko Akai
Affiliation:
Osaka National Research Institute, 1-8-31 Midorigaoka, Ikeda, Osaka 563, Japan
Masaru Yamashita
Affiliation:
Osaka National Research Institute, 1-8-31 Midorigaoka, Ikeda, Osaka 563, Japan
Hajimu Wakabayashi
Affiliation:
Yamamura Glass Co., Ltd., New Glass Research Center, 2-1-8 Naruohama, Nishinomiya, Hyogo 663, Japan.
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Abstract

Hydrated glass was prepared by the treatment in an autoclave. Specimen in a good state was obtained under unsaturated water vapor pressure conditions. The obtained glass has an silica-rich hydrated layer and proved to be more durable than the original glass. There are some kinds of hydroxyl species in the hydrated glass and there are some patterns in the depth profile of water, indicating that the rate-controlling process is not a simple diffusion and the hydration process is a complicated reaction depending on the conditions. Water in hydrated glass is tightly bonded and a disintegration of hydrated glass in this study occurs at more than 560°C.

Type
Research Article
Copyright
Copyright © Materials Research Society 1995

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References

REFERENCES

[1]. Lutze, W., Grambow, B., Ewing, R. C.. and Jercinovic, M. J.. in Natural Analogues in Radioactive Waste Disposal, edited by Come, B. and Chapman, N. A. (Graham & Trotman, London, 1987) pp. 142152.Google Scholar
[2]. Yamanaka, H., Wakabayashi, H., Yamashita, M., and Matsuoka, J., in The Third International Conference on Nuclear Fuel Reprocessing and Waste Management, Vol.II (Japan Atomic Industrial Forum, 1991), pp.10171021.Google Scholar
[3]. Bartholomew, R. F., in Treatise on Materials Science and Technology, Vol.22, edited by Tomozawa, M. and Doremus, R. H. (Academic Press, Inc., New York, 1982) pp.75127.Google Scholar
[4]. Williams, J. P., Su, Y. S., Hoover, H. L., and Altemose, V. O., Am. Ceram. Soc. Bull., 55, 524 (1976).Google Scholar
[5]. Shelby, J. E.. Vitko, J. Jr., and Benner, R. E., J. Am. Ceram. Soc., 65, C-59 (1982).Google Scholar
[6]. Bartholomew, R. F., Tick, P. A., and Stookey, S. D., J. Non-Cryst. Solids, 38&39, 637 (1980).Google Scholar
[7]. Monya, Y. and Nogami, M., J. Non-Cryst. Solids, 38&39, 667 (1980).Google Scholar
[8]. Wu, C.-K., J. Non-Cryst. Solids, 41, 381 (1980).Google Scholar