Published May 1979
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Vitrification of ICPP high-level zirconia calcine
Description
High-level radioactive calcined defense waste (approx. 50 wt % CaF2) is vitrified using a frit containing 66% SiO2, 24% Na2O, 8% B2O3, and 2% CuO. Effects of Na, B, Li, Zn, Cu, and P on viscosity and acid leach resistance were measured. The glass contains up to 9% fluoride. Glass properties were measured. 6 tables
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Additional details
Publishing Information
- Imprint Title
- Ceramics in nuclear waste management
- Journal Page Range
- p. 183-187.
- Report number
- CONF-790420--
Conference
- Title
- International symposium on ceramics in nuclear waste management.
- Dates
- 30 Apr - 2 May 1979.
- Place
- Cincinnati, OH, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11518357
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- HIGH-LEVEL RADIOACTIVE WASTES; IDAHO CHEMICAL PROCESSING PLAN; LEACHING; RADIOACTIVE WASTE PROCESSING; VITRIFICATION; ZIRCONIUM OXIDES
- Descriptors DEC
- CHALCOGENIDES; DISSOLUTION; FUEL REPROCESSING PLANTS; MANAGEMENT; NATIONAL ORGANIZATIONS; NUCLEAR FACILITIES; OXIDES; OXYGEN COMPOUNDS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; SEPARATION PROCESSES; TRANSITION ELEMENT COMPOUNDS; US AEC; US ERDA; US ORGANIZATIONS; WASTE MANAGEMENT; WASTE PROCESSING; WASTES; ZIRCONIUM COMPOUNDS