Characterization of simulated Al2O3-containing nuclear waste glass

Glass and glass-ceramics are an attractive waste form for the permanent disposal of high-level radioactive waste. Although typical waste sludge from the processing of spent reactor fuel contains more than 30 elements of wildly different ionic sizes and properties, these elements are chemically solub...

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Bibliographic Details
Published in:Journal of materials science 2004-05, Vol.39 (10), p.3533-3536
Main Authors: BONG KI RYU, BYUNG CHUL LEE, CHOE, Youngson, JONG RAK CHOI, PYUNG KOOK JI, CHEON WOO KIM, JONG HYUN HA, JONG KIL PARK, MYUNG JAE SONG
Format: Article
Language:English
Subjects:
Aluminum oxide
Applied sciences
Building materials. Ceramics. Glasses
Chemical industry and chemicals
Exact sciences and technology
Glasses
Materials science
Pollution
Radioactive wastes
Structure, analysis, properties
Wastes
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Summary:Glass and glass-ceramics are an attractive waste form for the permanent disposal of high-level radioactive waste. Although typical waste sludge from the processing of spent reactor fuel contains more than 30 elements of wildly different ionic sizes and properties, these elements are chemically soluble in many glass-forming compositions with reasonable chemical durability. The chemical corrosion of the waste by water is important since this corrosion could ultimately release biologically toxic radionuclides to the biosphere. In this study, the possibility of using the glass and glass-ceramics of Al2O3-containing sodium borosilicate as nuclear waste materials was examined and some infrared measurements were carried out to investigate the Na leaching mechanism as well as the influence of the controlled surface crystallization on effectively increasing the chemical durability.
ISSN:0022-2461
1573-4803
DOI:10.1023/B:JMSC.0000026970.02983.56