Published May 1979
| Version v1
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Utilization of borosilicate glass for transuranic waste immobilization
Description
Incinerated transuranic waste and other low-level residues have been successfully vitrified by mixing with boric acid and sodium carbonate and heating to 10500C in a bench-scale continuous melter. The resulting borosilicate glass demonstrates excellent mechanical durability and chemical stability
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Additional details
Publishing Information
- Imprint Title
- Ceramics in nuclear waste management
- Journal Page Range
- p. 338-341.
- 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
- 11518391
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BORIC ACID; BORON SILICATES; GLASS; HEATING; LOW-LEVEL RADIOACTIVE WASTES; RADIOACTIVE WASTE PROCESSING; SODIUM CARBONATES; STABILITY; TRANSURANIUM ELEMENTS; VITRIFICATION
- Descriptors DEC
- ALKALI METAL COMPOUNDS; BORON COMPOUNDS; CARBON COMPOUNDS; CARBONATES; ELEMENTS; HYDROGEN COMPOUNDS; INORGANIC ACIDS; MANAGEMENT; OXYGEN COMPOUNDS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; SILICATES; SILICON COMPOUNDS; SODIUM COMPOUNDS; WASTE MANAGEMENT; WASTE PROCESSING; WASTES