Hostname: page-component-77c78cf97d-lmk9j Total loading time: 0 Render date: 2026-04-23T16:42:50.294Z Has data issue: false hasContentIssue false
  • English
  • Français

Densification of Salt-Occluded Zeolite a Powders to a Leach-Resistant Monolith

Published online by Cambridge University Press:  25 February 2011

Michele A. Lewis ,
Donald F. Fischer  and
Christopher D. Murphy
Michele A. Lewis
Affiliation:
Argonne National Laboratory, Chemical Technology Division, Argonne, Illinois 60439
Donald F. Fischer
Affiliation:
Argonne National Laboratory, Chemical Technology Division, Argonne, Illinois 60439
Christopher D. Murphy
Affiliation:
Argonne National Laboratory, Energy Technology Division, Argonne, Illinois 60439
Get access

Abstract

Pyrochemical processing of spent fuel from the Integral Fast Reactor (IFR) yields a salt waste of LiCI-KCI that contains approximately 6 wt% fission products, primarily as CsCI and SrCl2. Past work has shown that zeolite A will preferentially sorb cesium and strontium and will encapsulate the salt waste in a leach-resistant, radiation-resistant aluminosilicate matrix. However, a method is still needed to convert the salt-occluded zeolite powders into a monolith suitable for geologic disposal. We are thus investigating a method that forms bonded zeolite by hot pressing a mixture of glass frit and sait-occluded zeolite powders at 990 K (717°C) and 28 MPa. The leach resistance of the bonded zeolite was measured in static leach tests run for 28 days in 363 K (90°C) deionized water. Normalized release rates of all elements in the bonded zeolite were low, <1 g/m2d. Thus, the bonded zeolite may be a suitable waste form for IFR salt waste.

Information

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 333: Symposium V – Scientific Basis for Nuclear Waste Management XVII , 1993 , 277
Copyright
Copyright © Materials Research Society 1994

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.)

Article purchase

Temporarily unavailable

References

References:

1 Laidler, J. J., Argonne National Laboratory, private communication (1992).Google Scholar
2 Lewis, M. A., Fischer, D. F., and Smith, L. J., “Salt-Occluded Zeolites as an Immobilization Matrix for Chloride Waste Salt,” accepted for publication, J. Am. Ceram. Soc. Google Scholar
3 Liquornik, M. and Marcus, Y., “Ion Exchange in Molten Salts II: The Occlusion of Lithium, Sodium, Potassium and Silver Nitrates in the Respective Forms of Zeolite A,” Israel J. Chem. 6,115–121 (1968).CrossRefGoogle Scholar
4 Jantzen, C. M., Bibler, N. E., Beam, D. C., Ramsey, W. G., and Waters, B. J., Standard Test Method for Evaluating Nuclear, Hazardous, and Mixed Waste Glass Durability: The Product Consistency Test (PCT), WSRC-TR-90-539, Rev.2, Westinghouse Savannah River Co. (1991).Google Scholar
5 Jantzen, C. M., Evaluation of Experimental Factors that Influence the Application and Discrimination Capability of the Product Consistency Test (U), WSRC-TR-90-526, Rev. 1, Westinghouse Savannah River (1991).CrossRefGoogle Scholar
6 Johnson, T. R. and Blaskovitz, R. J., Argonne National Laboratory, private communication (1992)Google Scholar
7 Nuclear Waste Materials Handbook, DOEmC-11400 (1982).Google Scholar
8 Plodenic, M. J., Wicks, G. G., and Bibler, N. E., An Assessment of Savannah River Borosilicate Glass in the Repository Environment, DP-1629, Savannah River Laboratory (1982).CrossRefGoogle Scholar
9 Winters, W.I., The Effect of Hot-Pressing Conditions on the Properties of Iodide Sodalite, RHO-LD-153, Rockwell International (1980).Google Scholar