Optimization of glass composition for the vitrification of nuclear waste at the Savannah River Plant Page: 4 of 26
26 pagesView a full description of this report.
Extracted Text
The following text was automatically extracted from the image on this page using optical character recognition software:
Currently, melting temperatures are limited to 1150°C by the
volatility of radionuclides such as cesium and ruthenium, which
means that the frit must be able to dissolve the waste at this
temperature. The resulting waste glass must be highly resistant
to aqueous attack.
An optimum frit was defined as one which produced waste glass
with a leachability as low as possible, with a maximum viscosity
at 1150°C as near 150 poise as possible, with a liquidus
temperature as low as possible, and with a coefficient of thermal
expansion as low as possible.
Such a frit composition was found after only 25 trials, in
spite of the fact that eight chemical components were studied.
This was achieved through application of the Nelder-Mead simplex
algorithm, which uses the frits themselves to point toward the
direction of improvement.
Properties and Optimization Criteria
Waste glasses made from each frit were compared in terms of
their viscosities, coefficients of thermal expansion, leach-
abilities and liquidus temperatures. Since the glass frit must
accommodate the entire range of waste compositions, each property
was measured under "worst case" conditions — high aluminum waste
for viscosities and high iron for the other three properties. The
waste compositions and concentrations are shown in Table 1. The
high-aluminum and high-iron waste simulations correspond to the
3
Upcoming Pages
Here’s what’s next.
Search Inside
This report can be searched. Note: Results may vary based on the legibility of text within the document.
Tools / Downloads
Get a copy of this page or view the extracted text.
Citing and Sharing
Basic information for referencing this web page. We also provide extended guidance on usage rights, references, copying or embedding.
Reference the current page of this Report.
Soper, P. D.; Roberts, G. J.; Lightner, L. F.; Walker, D. D. & Plodinec, M. J. Optimization of glass composition for the vitrification of nuclear waste at the Savannah River Plant, report, January 1, 1982; United States. (https://digital.library.unt.edu/ark:/67531/metadc1071607/m1/4/: accessed July 16, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.