Characterization on the high-level waste glasses. Annual report
Description
The waste compo itions PW-7c and PW-9 were defined and glass development was completed. Major variations in major oxide concentration would not grossly affect the leach rates of the glass. Impact and strength tests on nonradioactive glass showed that the waste glasses produced slightly less fine particulate than commercial glass. Waste glass had 60% of the strength of the soda-lime glass. A water-quench reduced thermal conductivity about 20%, and a 24-h hold at devitrification temperatures did not produce a significant change. Densities of waste glass at process temperature were 6.6 to 9.3% lower than at room temperature. The effects of glass composition on volatility were measured. Leach tests of highly devitrified samples of 72-68 have shown that leach rates of Cs, Sr and U are increased up to 10X and that Zn leach rates are reduced by nearly 200X. In glass 76-68, where devitrification is much slower, elemental differencesbetween as-formed and thermally-treated samples have not been significant. Average Cs leach rates from the 76-68 glass in an IAEA type long-term test have decreased to 3.3 x 10-8 g/cm2/day. High temperature (250 and 3500C) leach tests showed that glass is comparable to other ceramic materials. In salt brine the glass is rapidly depleted of Cs, Rb and Mo; in water the glass structure is rapidly rearranged to a crystalline structure, and Cs and Rb tend to remain bound in the solid. 76-68 glass (low ZnO) has slow devitrification kinetics compared to 72-68 glass (high ZnO). After equivalent radiation exposures of 300,000 years, the glass buttons still retain their original physical appearance. Stored energy is not a problem for HLW glasses. Density changes are small and do not affect the integrity of the samples
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A04/MF A01.Files
10446186.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 70 p.
- Report number
- PNL--2625
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 10446186
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Progress Report
- Descriptors DEI
- ALUMINIUM OXIDES; BRINES; CESIUM; CHEMICAL COMPOSITION; COMPARATIVE EVALUATIONS; CRYSTALLIZATION; DENSITY; GLASS; HIGH-LEVEL RADIOACTIVE WASTES; IMPACT TESTS; LEACHING; MECHANICAL PROPERTIES; MELTING; PERFORMANCE TESTING; QUANTITY RATIO; RADIATION EFFECTS; RADIOACTIVE WASTE PROCESSING; SEGREGATION; SIMULATION; SOLIDIFICATION; STRONTIUM; TEMPERATURE DEPENDENCE; THERMAL CONDUCTIVITY; TITANIUM OXIDES; URANIUM; VITRIFICATION; VOLATILITY; WATER; ZINC; ZINC OXIDES
- Descriptors DEC
- ACTINIDES; ALKALI METALS; ALKALINE EARTH METALS; ALUMINIUM COMPOUNDS; CHALCOGENIDES; DISSOLUTION; ELEMENTS; HYDROGEN COMPOUNDS; MANAGEMENT; MATERIALS TESTING; MECHANICAL TESTS; METALS; OXIDES; OXYGEN COMPOUNDS; PHASE TRANSFORMATIONS; PHYSICAL PROPERTIES; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; SEPARATION PROCESSES; TESTING; THERMODYNAMIC PROPERTIES; TITANIUM COMPOUNDS; TRANSITION ELEMENT COMPOUNDS; WASTE MANAGEMENT; WASTE PROCESSING; WASTES; ZINC COMPOUNDS