The role of frit in nuclear waste vitrification
Vitrification of nuclear waste requires additives which are often vitrified independently to form a frit. Frit composition is formulated to meet the needs of glass composition and processing. The effects of frit on melter feed and melt processing, glass acceptance, and waste loading is of practical interest in understanding the trade-offs associated with the competing demands placed on frit composition. 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 Plant.
- Research Organization:
- Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 10167545
- Report Number(s):
- PNL-SA-23487; CONF-940416-22; ON: DE94015212; TRN: 94:014656
- Resource Relation:
- Conference: 96. annual meeting of the American Ceramic Society (ACS),Indianapolis, IN (United States),25-28 Apr 1994; Other Information: PBD: Apr 1994
- Country of Publication:
- United States
- Language:
- English
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RADIOACTIVE WASTES
VITRIFICATION
WASTE FORMS
ADDITIVES
GLASS
MATERIALS TESTING
SILICON OXIDES
BORON OXIDES
LITHIUM OXIDES
SODIUM OXIDES
CALCIUM OXIDES
MAGNESIUM OXIDES
MECHANICAL PROPERTIES
EXPERIMENTAL DATA
052001
WASTE PROCESSING