Hostname: page-component-745bb68f8f-v2bm5 Total loading time: 0 Render date: 2025-02-04T16:33:41.387Z Has data issue: false hasContentIssue false
  • English
  • Français

Polyphase Ceramic and Glass-Ceramic forms for Immobilizing ICPP High-Level Nuclear Waste

Published online by Cambridge University Press:  25 February 2011

Alan B. Harker  and
John F. Flintoff
Alan B. Harker
Affiliation:
Rockwell International Science Center, P.O. Box 1085, 1049 Camino Dos Rios, Thousand Oaks, CA. 91360, USA
John F. Flintoff
Affiliation:
Rockwell International Science Center, P.O. Box 1085, 1049 Camino Dos Rios, Thousand Oaks, CA. 91360, USA
Get access

Abstract

Polyphase ceramic and glass-ceramic forms have been consolidated from simulated Idaho Chemical Processing Plant wastes by hot isostatic pressing calcined waste and chemical additives at 1000°C or less. The ceramic forms can contain over 70 wt% waste with densities ranging from 3.5 to 3.85 g/cm3, depending upon the formulation. Major phases are CaF2, CaZrTi2O7, CaTiO3, monoclinic ZrO2, and amorphous intergranular material. The relative fraction of the phases is a function of the chemical additives (TiO2, CaO, and Si02) and consolidation temperature. Zirconolite, the major actinide host, makes the ceramic forms extremely leach resistant for the actinide simulant U238. The amorphous phase controls the leach performance for Sr and Cs which is improved by the addition of SiO2. Glass-ceramic forms were also consolidated by HIP at waste loadings of 30 to 70 wt% with densities of 2.73 to 3.1 g/cm3 using Exxon 127 borosilicate glass frit. The glass-ceramic forms contain crystalline CaF2, Al2O3, and ZrSiO4 (zircon) in a glass matrix. Natural mineral zircon is a stable host for 4+ valent actinides.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 26: Symposium D – Scientific Basis for Nuclear Waste Management VII , 1983 , 513
Copyright
Copyright © Materials Research Society 1984

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. Harker, A.B., Morgan, P.E.D., Clarke, D.R., and Flintoff, J.F. in: Scientific Basis for Nuclear Waste Management vol 6, Topp, S.V. ed. (Elsevier, Amsterdam 1982) pp. 567–573.Google Scholar
2. Grantham, L.F., McKisson, R.L., Guon, J., Flintoff, J.F., and McKenzie, D.E., ESG-DOE-13397, Rockwell International Energy Systems Group Dept. of Energy Doc. No. DOE/ET/41900-16 (Feb. 1983).Google Scholar
3. DeWames, R.E., Grantham, L.F., Guon, J., and McKisson, R.L. in: Advances in Ceramics, Proc. of the Second International Symposium on Ceramics in Nuclear Waste Management, 85th Annual Meeting Am. Ceram. Soc., in press (Am. Ceram. Soc., Columbus, Ohio, 1983).Google Scholar
4. Berreth, J., Exxon Nuclear Idaho Co., Inc., Idaho Falls, Idaho, personal communication (1983).Google Scholar
5. Staples, B.A., Cole, H.S., and Mittl, J.C., ENICO-1095, Exxon Nuclear Idaho Co., Inc., (Sept. 1981).Google Scholar
6. Marker, A.B., Morgan, P.E.D., Flintoff, J.F., and Clarke, D.R., Proc. of the ANS Topical Meeting on the Treatment and Handling of Radioactive Waste (Battelle Press, Columbus, Ohio, 1982) pp. 335–340.Google Scholar
7. Harker, A.B. and Flintoff, J.F. in: Advances in Ceramics, Proc. of the Second International Symposium on Ceramics in Nuclear Waste Management, 85th Annual Meeting of the Am. Ceram. Soc., in press (Am. Ceram. Soc., Columbus, Ohio, 1983).Google Scholar
8. Harker, A.B., Morgan, P.E.D., and Flintoff, J.F., “Hot Isostatic Pressing of Nuclear Waste Glasses;” in press, J. Am. Ceram. Soc. (1983).Google Scholar
9. Morgan, P.E.D., Harker, A.B., Flintoff, J.F., Shaw, T.M., and Clarke, D.R. in: Advances in Ceramics, Proc. of the Second International Symposium on Ceramics in Nuclear Waste Management, 85th Annual Meeting of the Am. Ceram. Soc., in press (Am. Ceram. Soc., Columbus, Ohio, 1983).Google Scholar
10. Morgan, P.E.D., Shaw, T.M., and Pugar, E.A. in: Waste Management 83, Proc. Symposium on Waste Management, Tucson, Arizona Vol 2, Post, R.G., ed. (U. of Ariz., 1983) pp. 207–212.Google Scholar
11. Morgan, P.E.D., Shaw, T.M. and Pugar, E.A. in: Advances in Ceramics, Proc. of the Second International Symposium on Ceramics in Nuclear Waste Management, 85th Annual Meeting of the Am. Ceram. Soc., in press (Am. Ceram. Soc., Columbus, Ohio, 1983).Google Scholar
12. Morgan, P.E.D. and Cirlin, E.H., J. Am. Ceram. Soc. 65, C114–C115 (1982).Google Scholar
13. Mendel, J., Materials Characterization Test Methods, PNL-3990. Battelle Pacific Northwest Laboratories, Richland, WA. (1982).Google Scholar
14. Cole, H.S., Gombert, D., and Berreth, J.R., ENICO-1038, Exxon Nuclear Idaho Co., Inc., Idaho Falls, Idaho (1980).Google Scholar
15. Haggerty, S.E., Raber, E., and Naeser, C.W., Earth and Planet. Sci. Let. 63, pp. 41–50 (1983).Google Scholar
16. Staples, B.A., Pavlica, D.A., and Cole, H.S., ENICO-1120, Exxon Nuclear Idaho Co., Inc., Idaho Falls, Idaho (1982).Google Scholar
17. Ackerman, F.J., Grens, J.Z., Ryerson, F.J., Hoenig, C.L., Bazan, F., Peters, P.E., Smith, R., and Campbell, J.H., UCRL-53405, Lawrence Livermore National Laboratory (Mar. 1983).Google Scholar