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Systematic Composition Studies on the Durability of Waste Glass WV205

Published online by Cambridge University Press:  28 February 2011

Xiangdong Feng ,
Aaron Barkatt  and
Tian Jiang
Xiangdong Feng
Affiliation:
The Vitreous State Laboratory, The Catholic University of America, Washington, D.C. 20064
Aaron Barkatt
Affiliation:
The Vitreous State Laboratory, The Catholic University of America, Washington, D.C. 20064
Tian Jiang
Affiliation:
The Vitreous State Laboratory, The Catholic University of America, Washington, D.C. 20064
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Abstract

A systematic study of the chemical durability of glass compositions developed for the immobilization of high-level radioactive wastes at West Valley is described. Most of the compositions studied here represent variations around the nonradioactive WV205 composition. The results from this study indicate that the effectiveness of the various oxides tested in increasing the durability of WV205, when considered in terms of 2% additions by weight to the central composition, decreases in the following order: A12O3>ZrO2>SiO2>Cr2O3>Fe2O3>TiO2>CuO>ZnO>NiO. The addition of 2–6% Cr2O3 or NiO to WV205 was observed to cause extensive crystallization. The addition of 2% or 6% ZnO or 2% TiO2, CuO or NiO to the glass actually enhances corrosion rates. A12O3 and ZrO2 are the best additives in terms of increasing the durability. The additions of ThO2 and U3O8 slightly increase the durability. The effects of various oxides on the durability of WV-205-based glasses with ThO2 and U3O8 were found to be very similar to the effects of these oxides on the durability of the corresponding glasses which did not contain ThO2 and U3O8. This study also showed that Fe2O3 has little effect on the durability. However, FeO greatly enhances the corrosion rates of WV205-based glasses. Much less pronounced effects of the redox state of iron were found in the case of more durable base glass compositions.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 112: Symposium P – Scientific Basis for Nuclear Waste Management XI , 1987 , 673
Copyright
Copyright © Materials Research Society 1988

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