Vitrification and chemical durability of simulated high-level nuclear waste glasses with high concentrations of Cr{sub 2}O{sub 3} and Al{sub 2}O{sub 3}
Conference
·
OSTI ID:518682
- Pacific Northwest Lab., Richland, WA (United States); and others
Borosilicate glasses were loaded with 30 to 55 wt% of simulated high-level tank waste, rich in Cr{sub 2}O{sub 3} and Al{sub 2}O{sub 3}, obtained from Hanford Site (Richland, Washington). No segregated chromate was observed on molten glass at the melting temperature. Eskolaite (Cr{sub 2}O{sub 3} with iron) and chromite (FeCr{sub 2}O{sub 4}) crystals were found in all quenched glasses. At waste loadings {ge}50 wt%, nephelme (NaAlSiO{sub 4}) and beta-eucryptite ({beta}-LiAlSiO{sub 4}) became major crystalline phases. Precipitation of these phases decreased melt viscosity and glass corrosion resistance.
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 518682
- Report Number(s):
- CONF-9604124--
- Country of Publication:
- United States
- Language:
- English
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