Hostname: page-component-7bb8b95d7b-pwrkn Total loading time: 0 Render date: 2024-09-27T01:30:48.702Z Has data issue: false hasContentIssue false

Demonstration of the Feasibility of Recovering Americium and Curium Isotopes from a Lanthanide Borosilicate Glass

Published online by Cambridge University Press:  21 March 2011

Tracy S. Rudisill
Affiliation:
Westinghouse Savannah River Company Aiken, SC 29808
David K. Peeler
Affiliation:
Westinghouse Savannah River Company Aiken, SC 29808
Thomas B. Edwards
Affiliation:
Westinghouse Savannah River Company Aiken, SC 29808
Get access

Abstract

A solution containing kilogram quantities of highly radioactive isotopes of americium and curium (Am/Cm) is currently stored in a process tank at the Department of Energy's Savannah River Site. This tank and its vital support systems are old, subject to deterioration, and prone to possible leakage. To address the stabilization of this material, vitrification of the isotopes has been considered. Potentially, the glass could be shipped to the isotope production and distribution programs at the Oak Ridge National Laboratory for californium-252 production and use by the transplutonium research community. However, before the Am/Cm could be used in these programs, it must be recovered from the glass.

To demonstrate the feasibility of recovering the Am/Cm isotopes from a glass, a series of small-scale experiments was performed as part of a compositional variability study. Glasses fabricated during the study utilized lanthanide elements as surrogates for Am/Cm due to the high specific activity of these materials. In the dissolution tests, glass formulations representative of potential uncertainties in the composition of the Am/Cm solution were fabricated, ground to a -35 to +60 mesh particle size, and dissolved in 8M nitric acid at 110°C. Under these conditions, at least 98% of the lanthanide oxides in the glass dissolved in less than 2 h meeting a recoverability criterion established for the vitrification process and imposing no limitations on the acceptable glass composition region.

Dissolution of the lanthanide borosilicate glasses was described by a spherical particle model based on the observation that the rate of change of the mass to surface area ratio remains constant. Calculation of dissolution rates using the model showed that the rate was proportional to the lanthanide oxide concentration in the glass. When silicon oxide (SiO2) was replaced with a lanthanide element at higher (simulated Am/Cm) loadings, the glass became more easily dissolved in nitric acid due to the solubility of the lanthanide oxides compared to SiO2.

Type
Research Article
Copyright
Copyright © Materials Research Society 2002

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. Rudisill, T. S., Pretreatment of Americium/Curium Solutions for Vitrification, Report No. WSRC-TR-96-0074, Westinghouse Savannah River Company, Aiken, SC (March 1996).Google Scholar
2. Conway, J. T., “Recommendation 94-1 to the Secretary of Energy pursuant to 42 U.S.C. [paragraph] 2286a(5) Atomic Energy Act of 1954, as amended” (Attachment), Letter from Defense Nuclear Facilities Safety Board to Secretary of Energy, Washington, DC (1994).Google Scholar
3. Collins, E. D., Klein, J. A., Knauer, J. B. Jr, Alexander, C. W., Mirzadeh, S., Aaron, W. S., and Cline, R. L., Oak Ridge Isotope Products and Services – Current and Expected Supply and Demand, Report No. ORNL/CP-103243, Oak Ridge National Laboratory, Oak Ridge, TN (August 1999).Google Scholar
4. Ramsey, W. G., Miller, D., Minichan, R., Colman, L., Schumacher, R., Hardy, B., and Jones, R., Vitrification of F-Area Americium/Curium: Feasibility Study and Preliminary Process Recommendation, Report No. WSRC-TR-94-0211, Westinghouse Savannah River Company, Aiken, SC (April 1994).Google Scholar
5. Rudisill, T. S., Pareizs, J. M., and Ramsey, W. G. in Scientific Basis for Nuclear Waste Management XX, edited by Gray, W. J. and Triay, I. R. (Mater. Res. Soc. Proc. 465, Pittsburgh, Pa, 1996).Google Scholar
6. Peeler, D. K, Edwards, T. B., Reamer, I. A., Vienna, J. D., Smith, D. E., Schweiger, M. J., Riley, B. J., and Crum, J. V., Composition/Property Relationship for the Phase 1 Am/Cm Glass Variability Study, Report No. WSRC-TR-99-00055, Westinghouse Savannah River Company, Aiken, SC (January 1999).Google Scholar
7. Peeler, D. K, Edwards, T. B., Rudisill, T. S., Reamer, I. A., Vienna, J. D., Smith, D. E., Schweiger, M. J., and Riley, B. J., Composition/Property Relationship for the Phase 2 Am-Cm Glass Variability Study, Report No. WSRC-TR-99-00393, Westinghouse Savannah River Company, Aiken, SC (May 2000).Google Scholar
8. Greenwood, N. N. and Earnshaw, A., Chemistry of the Elements, Pergamon Press (New York, NY, 1989) p. 1437.Google Scholar
9. Cotton, F. A. and Wilkinson, G., Advanced Inorganic Chemistry, 5th ed. (John Wiley and Sons, Inc., New York, NY, 1988) pp. 278279.Google Scholar