Hostname: page-component-586b7cd67f-rdxmf Total loading time: 0 Render date: 2024-11-25T20:28:43.516Z Has data issue: false hasContentIssue false
  • English
  • Français

Actinide Solubility in Lanthanide Borosilicate Glass for Possible Immobilization and Disposition

Published online by Cambridge University Press:  03 September 2012

T. F. Meaker ,
D. K. Peeler ,
J. C. Marra ,
J. M. Pareizs  and
W. G. Ramsey
T. F. Meaker
Affiliation:
Savannah River Laboratory, Savannah River Site, Aiken, SC, 29808
D. K. Peeler
Affiliation:
Savannah River Laboratory, Savannah River Site, Aiken, SC, 29808
J. C. Marra
Affiliation:
Savannah River Laboratory, Savannah River Site, Aiken, SC, 29808
J. M. Pareizs
Affiliation:
Savannah River Laboratory, Savannah River Site, Aiken, SC, 29808
W. G. Ramsey
Affiliation:
Savannah River Laboratory, Savannah River Site, Aiken, SC, 29808
Get access

Abstract

Immobilization by vitrification is one potential disposition option for a portion of the United States’ excess plutonium inventory. Research has been performed to determine the glass forming region of a frit, plutonium and rare earth system. The frit contains mainly oxides of aluminum, silicon and boron; small amounts of ZrO2 and SrO are also included. The rare earth elements provide a flux to the glass during processing. The rare earths are also added as neutron absorbers (to prohibit criticality) in the final vitreous product.

This report will show the compositional region, using Th as a Pu surrogate, that should be targeted in future studies for maximum Pu solubility in the lanthanide borosilicate glass system. Durability data and process variables will also be provided.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 465: Symposium II – Scienfific Basis for Nuclear Waste Management XX , 1996 , 1281
Copyright
Copyright © Materials Research Society 1997

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. Vienna, J.D., et al. , “Plutonium Dioxide Dissolution in Glass”, PNNL-11346, Pacific Northwest National Laboratory, Richland, WA, (September 1996).10.2172/416955Google Scholar
2. Bibler, N.E., Ramsey, W.G., Meaker, T.F. and Pareizs, J.M., “Durabilities and Microstructures of Radioactive Glasses for Immobilization of Excess Actinides at the Savannah River Site”, Materials Research Society Symposia Proceedings, Vol. 233, pp. 333–336, Materials Research Society, Pittsburgh, PA (1995).Google Scholar
3. Meaker, T.F., “Effects of Periodic Manual Stirring and Uranium Addition on Surrogate Plutonium Glass Processing”, WSRC-TR-96–0321, Westinghouse Savannah River Company, Aiken, SC, (September, 1996)10.2172/481473Google Scholar
4. Meaker, T.F., “Compositional Development of a Lanthanide Borosilicate Glass for Plutonium Immobilization Without Listed RCRA Materials (Lead and Barium) (U)”, WSRC-TR-96–0322, Westinghous Savannah River Company, Aiken, SC, (September 1996).10.2172/518762Google Scholar
5. Jantzen, C.M., Bibler, N.E., Beam, D.C., and Ramsey, W.G., “Nuclear Waste Glass Product Consistency Test (PCT) - Version 7.0 (U)”, USDOE Report WSRC-TR-90–539, Rev. 3, Westinghouse Savannah River Co., Aiken, SC (June 1994).10.2172/10176796Google Scholar
6. Figure No. 763, Phase Diagrams for Ceramists, American Ceramic Society, (1996).Google Scholar
7. Mellinger, G.B., and Daniel, J.L., “Approved Reference and Testing Materials for Use in Nuclear Waste Management Research and Deveolopment Programs”, U.S. DOE Report PNL-4955–2, Materials Characterization Center, Batelle Pacific Northwest Laboratory, Richland, WA, (December 1984).10.2172/6224421Google Scholar