Hostname: page-component-586b7cd67f-dlnhk Total loading time: 0 Render date: 2024-11-29T07:22:24.579Z Has data issue: false hasContentIssue false
  • English
  • Français

Basis for Selecting Cement-Based Waste Forms for Immobilizing Radioactive Waste

Published online by Cambridge University Press:  26 February 2011

Earl W. Mcdaniel ,
Othar K. Tallent ,
Terry L. Sams ,
Dianne B. Delzer  and
William D. Bostick
Earl W. Mcdaniel
Affiliation:
Chemical Technology Division, Oak Ridge National Laboratory, Post Office Box 2003, Oak Ridge, Tennessee, U.S.A.
Othar K. Tallent
Affiliation:
Chemical Technology Division, Oak Ridge National Laboratory, Post Office Box 2003, Oak Ridge, Tennessee, U.S.A.
Terry L. Sams
Affiliation:
Waste Management Training Center, Roane State Community College, Oak Ridge, Tennessee, U.S.A.
Dianne B. Delzer
Affiliation:
Quality and Technical Services Division, Oak Ridge Gaseous Diffusion Plant, Post Office Box 2003, Oak Ridge, Tennessee, U.S.A.
William D. Bostick
Affiliation:
Quality and Technical Services Division, Oak Ridge Gaseous Diffusion Plant, Post Office Box 2003, Oak Ridge, Tennessee, U.S.A.
Get access

Abstract

Research at Oak Ridge National Laboratory (ORNL) has shown that cement-based waste forms can be tailored to tolerate wide fluctuations in waste-feed compositions and still maintain properties that are compatible with standard equipment and produce a product that meets regulatory requirements. The 20-year operational history of ORNL's grouting program has demonstrated this resilience and reliability on a spectrum of waste feeds encompassing the developmental history of the nuclear fuel cycle.

Cement-based materials are the most frequently used waste forms for solidifying non-high-level waste. These materials are also perhaps the most misused for immobilizing wastes. This paper discusses the scientific basis for selecting a suitable cement-based waste form to solidify and immobilize radioactive waste. For instance, when a given amount of cement (the source of calcium) is replaced with class F fly ash, the strontium leachability is reduced proportionally.

This paper discusses the use of gel clays such as bentonite and attapulgite to absorb excess fluids and thus increase waste loading. Also, cement-compatible natural materials such as nonswelling clays are used to ion exchange or absorb soluble ions such as cesium and thus reduce leachability.

Recently, blast furnace slag has been the subject of much interest in cement-based immobilization technology. Data are presented to show that a waste form containing blast furnace slag and other cementing materials is very effective in reducing the release rates of 99Tc.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 127: Symposium BERLIN – Scientific Basis for Nuclear Waste Management XII , 1988 , 421
Copyright
Copyright © Materials Research Society 1989

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. de Laguna, W. et al., Engineering Development of Hydraulic Fracturing as a Method for Permanent Disposal of Radioactive Wastes, ORNL-4259, Union Carbide Corporation, Oak Ridge National Laboratory, Oak Ridge, Tennessee, August 1968.Google Scholar
2. Tallent, O. K. et al., Initial Formulation Results for In Situ Grouting of a Waste Trench at ORNL Site No. 6. ORNL/TM-10299, Martin Marietta Energy Systems, Oak Ridge National Laboratory, Oak Ridge, Tennessee, January 1987.Google Scholar
3. Moore, J. G., Development of Cementitious Grouts for the Incorporation of Radioactive Wastes. Part 2: Continuation of Cesium and Strontium Leach Studies. ORNL-5142, Union Carbide Corporation, Oak Ridge National Laboratory, Oak Ridge, Tennessee, September 1976.Google Scholar
4. Gilliam, T. M., McDaniel, E. W. et al., Summary Report on the Development of a Cement-Based Formula to Immobilize Hanford Facility Waste, ORNL/TM-10141, Martin Marietta Energy Systems, Oak Ridge National Laboratory, Oak Ridge, Tennessee, September 1987.CrossRefGoogle Scholar
5. Tallent, O. K., McDaniel, E. W., Del Cui, G. D., Dodson, K. E., and Trotter, D. R., “Immobilization of Technetium and Nitrate in Cement-based Materials,” presented at the Materials Research Society Symposium, November 30 - December 3, 1987, Boston, Massachusetts.Google Scholar
6. “Measurement of Leachability of Solidified Low-Level Radioactive Wastes by a Short-Term Test Procedure, ANSI/ANS-16.1–1986,” American National Standard. American Nuclear Society, 555 North Kensington Avenue, LaGrange Park, Illinois 60525, April 1986.Google Scholar
7. United States Federal Register 40 CFR 261.24).Google Scholar