Glass products for the vitrification of HLLW in a joule-heated ceramic melter and the effects of platinoids on the glass properties
Creators
- 1. Kernforschungszentrum Karlsruhe GmbH (Germany). Inst. fuer Nukleare Entsorgungstechnik
Description
A vitrification process was developed at KfK/INE for the solidification of HLW-solutions from the nuclear fuel cycle as borosilicate glasses. To optimize melter operation the glass melt should have a flat viscosity curve and a relatively high specific electrical resistance of > 6 Ω · cm at 1,150 C. Further requirements are: no liquid-liquid immiscibility and no crystallization of the glass, waste loading > 15 wt.% and with a view to final storage of the HLW glass a chemical durability comparable to other HLW glasses. Experimental work was geared to adjusting the viscosity and the electrical resistance to the required values by varying the chemical composition of the glass. By use of mixed-alkali glasses containing Li2O and Na2O, glasses can be prepared which meet the required properties. In the technical vitrification process the platinoids Ru, Rh and Pd form precipitates and accumulate on the bottom of the melter. Dense sediments are formed with a lower resistance and a higher viscosity than those of the rest of the glass melt. Glass samples with about 16 wt.% platinoids have a very low resistance of only 0.1 Ω · cm and show a non-Newtonian, pseudoplastic flow behavior
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-0691-X
- Imprint Title
- Proceedings of the 1993 international conference on nuclear waste management and environmental remediation. Volume 1: Low and intermediate level radioactive waste management
- Imprint Pagination
- 776 p.
- Journal Page Range
- p. 427-433.
Conference
- Title
- '93 international conference on nuclear waste management and environmental remediation.
- Dates
- 5-11 Sep 1993.
- Place
- Prague (Czech Republic).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27008909
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- ADDITIVES; BOROSILICATE GLASS; CHEMICAL COMPOSITION; CORROSION RESISTANCE; ELECTRIC CONDUCTIVITY; EXPERIMENTAL DATA; HIGH-LEVEL RADIOACTIVE WASTES; LIQUID WASTES; LITHIUM OXIDES; PALLADIUM; PHASE DIAGRAMS; PHYSICAL PROPERTIES; RADIOACTIVE WASTE PROCESSING; RHODIUM; RUTHENIUM; SODIUM OXIDES; TECHNOLOGY ASSESSMENT; VITRIFICATION; WASTE FORMS
- Descriptors DEC
- ALKALI METAL COMPOUNDS; CHALCOGENIDES; DATA; DIAGRAMS; ELECTRICAL PROPERTIES; ELEMENTS; GLASS; INFORMATION; LITHIUM COMPOUNDS; MANAGEMENT; MATERIALS; METALS; NUMERICAL DATA; OXIDES; OXYGEN COMPOUNDS; PLATINUM METALS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; SODIUM COMPOUNDS; TRANSITION ELEMENTS; WASTE MANAGEMENT; WASTE PROCESSING; WASTES
Optional Information
- Secondary number(s)
- CONF-930906--.