Hostname: page-component-7479d7b7d-q6k6v Total loading time: 0 Render date: 2024-07-11T22:12:07.010Z Has data issue: false hasContentIssue false
  • English
  • Français

Optimization of Lanthanide Borosilicate Frit Compositions for the Immobilization of Actinides Using a Plackett-Burman/Simplex Algorithm Design

Published online by Cambridge University Press:  03 September 2012

M. G. Mesko ,
T. F. Meaker ,
W. G. Ramsey ,
J. C. Marra  and
D. K. Peeler
M. G. Mesko
Affiliation:
University of Missouri-Rolla, Rolla, MO 65401mesko@umr.edu
T. F. Meaker
Affiliation:
University of Missouri-Rolla, Rolla, MO 65401mesko@umr.edu
W. G. Ramsey
Affiliation:
University of Missouri-Rolla, Rolla, MO 65401mesko@umr.edu
J. C. Marra
Affiliation:
Westinghouse Savannah River Co., Aiken SC 29808
D. K. Peeler
Affiliation:
Westinghouse Savannah River Co., 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 at the Savannah River Site (SRS) to determine the optimum composition of a lanthanide borosilicate frit for the vitrification of plutonium using a Plackett-Burman design and simplex algorithm as a statistical tool. This technique uses various response variables to rank and optimize a composition. The variables used in this study correspond to homogeneity, durability, actinide solubility and devitrification after heat-treatment.

The optimized frit composition was determined using a constant ThO2 loading of 20 wt%. No noticeable trends were followed with respect to the individual components which may indicate a relatively robust system able to accommodate variations in the feed.

Batches containing various loadings of ThO2 were melted to determine if actinide solubility was improved in the optimized composition compared to that of a similar lanthanide borosilicate glass. No noticeable improvement in ThO2 solubility was realized as a result of using this optimization technique.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 465: Symposium II – Scienfific Basis for Nuclear Waste Management XX , 1996 , 105
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 Bates, J. K., Ellison, A. J. G., Emery, J. W., and Hoh, J. C., Glass as a Waste Form for the Immobilization of Plutonium, in Scientific Basis for Nuclear Waste Management XIX, edited by Murphy, W. M. and Knecht, D. A., (Mater. Res. Soc. Proc, Pittsburgh, PA, 1995), p. 57.Google 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, in Scientific Basis for Nuclear Waste Management XIX, edited by Murphy, W. M. and Knecht, D. A., (Mater. Res. Soc. Proc, Pittsburgh, PA, 1995), p. 65.Google Scholar
3 “Strategy of Experimentation”, E. I. duPont de Nemours & Co., Wilmington, DE, 1988.Google Scholar
4 Immobilization Program Peer Review, Lawrence Livermore National Laboratory, April 24–25, 1996.Google Scholar
5 ASTM C 1285–94Google Scholar
6 Savannah River Technology Center, Aiken, SCGoogle Scholar