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Cementitious Radioactive Waste Hosts Formed Under Elevated Temperatures and Pressures (Fuetap Concretes)*

  • L. R. Dole (a1), J. G. Moore (a1), G. C. Rogers (a1), G. A. West (a1), H. E. Devaney (a1), M. T. Morgan (a1), E. W. Mcdaniel (a1) and J. H. Kessler (a1)...

Abstract

Concretes formed under elevated temperatures and pressures (FUETAP concretes) are effective hosts for transuranic (TRU) and high-level defense and commercial wastes.

Tailored cement formulations developed at Oak Ridge National Laboratory (ORNL) use Portland cement, fly ash, sand, and clay additives. These FUETAP concretes are cured under mild autoclave conditions, then the unbound water is removed.

This paper summarizes the FUETAP development program. These continuous studies address the major questions concerning the performance of radioactive waste forms.

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*

Research sponsored by the Office of Waste Operations and Technology, U.S. Department of Energy under contract W–7405–eng–26 with the Union Carbide Corporation.

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References

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1. Moore, J. G. et al. in: Proceedings of the International Seminar on Chemistry and Process Engineering for High-Level Liquid Waste Solidification (Kernforschungsanlage, Julich, Federal Republic of Germany 1981).
2. Moore, J. G. in: Proceedings of a Workshop on Alternative Nuclear Waste Forms and Interactions in Geologic Media, CONF–8005107, Boatner, L. A. and Battle, G. C. Jr. eds. (Technical Information Center, Oak Ridge, Tennessee 1981) p. 194.
3. Moore, J. G. et al. . in: Proceedings of the Symposium on Waste Management, Waste Management 1981 Conference, Vol 1, Post, R. G. ed. (Tucson, Arizona 1981) p. 277.
4. Moore, J. G., Newman, E. and Rogers, G. C., Radioactive Waste Fixation in FUETAP (Formed Under Elevated Temperatures and Pressure) Concrete Experimental Program and Initial Results, ORNL/TM–6573 (March 1979).
5. Moore, J. G. et al. . in: Proceedings of the Conference on Ceramics in Nuclear Waste Management, CONF–790420, Chikalla, T. D. and Mendel, J. E., eds. (Technical Information Center, Oak Ridge, Tennessee 1979) p. 132.
6. Post, R. G., Panel Chairman, Independent Review Panel to Evaluate and Review Alternative Waste Forms to Immobilize the Idaho Chemical Processing Plant (ICPP) Waste: Final Report, ENICO–1088 (Exxon Nuclear Idaho Co., Idaho Falls, Idaho 1981).
7. Weeren, H. O. and Perona, J. J., A Preliminary Engineering and Economic Analysis of the Fixation of High-Level Radioactive Wastes in Concrete, ORNL/TM-6863 (July 1979).
8. Johnson, E. R. Associates, Inc., Preliminary Evaluation of Alternative Waste Form Solidification Processes, Vol. II: Evaluation of the Processes, PNL–3477 (Pacific Northwest Laboratory, Richland, Washington 1980).
9. Stone, J. A. et al. ., Preliminary Evaluation of Alternative Forms for Immobilization of Savannah River Plant High-Level Waste, DP–1545 (DuPont de Nemours and Company, Aiken, South Carolina 1979).
10. Strachan, D. M., Barnes, B. O. and Turcotte, R. P. in: Conference on the Scientific Basis for Nuclear Waste Management, Vol. 3, Moore, J. G. ed. (Plenum Press, New York 1981) p. 341.
11. Godbee, H. W. et al. . in: “Application of Mass Transport Theory to the Leaching of Radionuclides from Waste Solids,” Nucl. Chem. Waste Manage., 1, 29 (1980).
12. Moore, J. G., Godbee, H. W. and Kibbey, A. H., Nucl. Tech. 3, 39 (January 1977).
13. Bibler, N. E. in: Proceedings of the Conference on the Scientific Basis for Nuclear Waste Management, Vol. 2, Northrup, C. J. M. ed. (Plenum Press, New York 1980), pp. 585592.
14. Katz, S. in: Proceedings of the Conference on the Scientific Basis for Nuclear Waste Management, Vol. 2, Moore, J. G. ed. (Plenum Press, New York 1980), pp. 577584.
15. Kazanjian, A. R. and Killion, M. E., Radiolytic Gas Generation from Sludge, CRD 81–025 (Rockwell International, Rocky Flats, Colorado 1981).
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MRS Online Proceedings Library (OPL)
  • ISSN: -
  • EISSN: 1946-4274
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