Title of article
Tellurite glass as a waste form for mixed alkali–chloride waste streams: Candidate materials selection and initial testing
Author/Authors
Riley، نويسنده , , Brian J. and Rieck، نويسنده , , Bennett T. and McCloy، نويسنده , , John S. and Crum، نويسنده , , Jarrod V. and Sundaram، نويسنده , , S.K. and Vienna، نويسنده , , John D.، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2012
Pages
9
From page
29
To page
37
Abstract
Tellurite glasses have historically been shown to host large concentrations of halides. They are here considered for the first time as a waste form for immobilizing chloride wastes, such as may be generated in the proposed molten alkali salt electrochemical separations step in nuclear fuel reprocessing. Key properties of several tellurite glasses are determined to assess acceptability as a chloride waste form. TeO2 glasses with other oxides (PbO, Al2O3 + B2O3, WO3, P2O5, or ZnO) were fabricated with and without 10 mass% of a simulated (non-radioactive) mixed alkali, alkaline-earth, and rare earth chloride waste. Measured chemical durability is compared for the glasses, as determined by the product consistency test (PCT), a common standardized chemical durability test often used to validate borosilicate glass waste forms. The glass with the most promise as a waste form is the TeO2–PbO system, as it offers good halide retention, a low sodium release (by PCT) comparable with high-level waste silicate glass waste forms, and a high storage density.
Journal title
Journal of Nuclear Materials
Serial Year
2012
Journal title
Journal of Nuclear Materials
Record number
1360838
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