The role of frit in nuclear waste vitrification
Conference
·
OSTI ID:39191
- Pacific Northwest Lab., Richland, WA (United States)
Melter feed yield stress, viscosity and durability of frits and corresponding waste glasses as well as the kinetics of elementary melting processes have been measured. The results illustrate the competing requirements on frit. Four frits (FY91, FY93, HW39-4, and SR202) and simulated neutralized current acid waste (NCAW) were used in this study. The experimental evidence shows that optimization of frit for one processing related property often results in poorer performance for the remaining properties. The difficulties associated with maximum waste loading and durability are elucidated for glasses which could be processed using technology available for the previously proposed Hanford Waste Vitrification Plan.
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 39191
- Report Number(s):
- CONF-940416--
- Country of Publication:
- United States
- Language:
- English
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