Hostname: page-component-77c89778f8-vpsfw Total loading time: 0 Render date: 2024-07-19T09:15:07.660Z Has data issue: false hasContentIssue false
  • English
  • Français

Leaching Studies of Cement-Glass Package Containing Sodium Borate

Published online by Cambridge University Press:  28 February 2011

Masahiro Okamoto ,
Koichi Chino ,
Tsutomu Baba ,
Tatsuo Izumida ,
Fumio Kawamura  and
Makoto Kikuchi
Masahiro Okamoto
Affiliation:
Kansai Electric Power Co., Osaka, Japan
Koichi Chino
Affiliation:
Energy Research Laboratory, Hitachi Ltd., 1168 Moriyama, Hitachi, Ibaraki 316, Japan
Tsutomu Baba
Affiliation:
Energy Research Laboratory, Hitachi Ltd., 1168 Moriyama, Hitachi, Ibaraki 316, Japan
Tatsuo Izumida
Affiliation:
Energy Research Laboratory, Hitachi Ltd., 1168 Moriyama, Hitachi, Ibaraki 316, Japan
Fumio Kawamura
Affiliation:
Energy Research Laboratory, Hitachi Ltd., 1168 Moriyama, Hitachi, Ibaraki 316, Japan
Makoto Kikuchi
Affiliation:
Hitachi Works, Hitachi Ltd., 3-1-1 Saiwaicho, Hitachi, Ibaraki 317, Japan
Get access

Abstract

A new solidification technique using cement-glass, which is a mixture of sodium silicate, cement, additives, and initiator of the solidification reaction, was developed for sodium borate liquid waste generated from pressurized water reactor (PWR) plants. The cement-glass could solidify eight times as much sodium borate as cement could, because the solidifying reaction of the cement-glass is not hindered by borate ions.

The reaction mechanism of sodium silicate and phosphoric silicate (initiator), the main components of cement-glass, was studied through X-ray diffraction and compressive strength measurements. It was found that three- dimensionally bonded silicon dioxide was produced by polymerization of the two silicates. The leaching ratio of cesium from the cement-glass package was one-tenth that of the cement one. This low value was attributed to a high cesium adsorption ability of the cement-glass and it could be theoretically predicted accordingly.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 84: Symposium L – Scientific Basis for Nuclear Waste Management X , 1986 , 393
Copyright
Copyright © Materials Research Society 1987

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

1. Kikuchi, M., Chino, K., Kudo, K., Horiuchi, S., Saito, T., and Hayashi, M., in Waste Management '81, edited by Post, R. G. (Arizona Board of Regents, Tucson, 1981) vol.2 pp.547–568.Google Scholar
2. Kikuchi, M., Chino, K., Koyama, T., Ito, T., Yusa, H., Horiuchi, S., and Hayashi, M., in Waste Management '82 edited by Post, R. G. (Arizona Board of Regents, Tucson, 1982) vol.2 pp.601–610.Google Scholar
3. Okamoto, M., Kawamura, F., Izumida, T., Chino, K., Kikuchi, M., and Mizuno, H., Trans. Am. Nucl. Soc., 49 74 (1985)Google Scholar
4. Seki, S., JAERI Report No. M-9762-,1982 Google Scholar
5. Glasser, L. S. Dent, Chemistry in Britain, Jan. 33 (1982)Google Scholar
6. Glasser, L. S. Dent, J. Chem. Soc. Dalton Trans,. 399 (1980)Google Scholar
7. Emura, S., Matsuzuru, H., Hisa, I., and Seki, S., JAERI Report No. M-5779 (1974)Google Scholar
8. Muurine, A., Rantanen, J., and Ovaskainen, R., in Scientific Basis for Nuclear Waste Management VIII, edited by Jantzen, C. M. (Material Research Society, Pittsburge, 1985). pp. 883–890 Google Scholar