The Preparation and Characterization of INTEC Phase 2b Composition Variation Study Glasses

Technical Report · Tue Feb 01 04:00:00 EST 2000

DOI:https://doi.org/10.2172/768819· OSTI ID:768819

Staples, B A ^[1]; Scholes, B A; Torres, L L; Musick, C A; Boyle, B R ^[2]; Peeler, D K ^[3]; Vienna, J D ^[4]

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1. Idaho National Engineering and Environmental Laboratory
2. INEEL
3. SRTC
4. PNNL

The second phase of the composition variation study (CVS) for the development of glass compositions to immobilize Idaho Nuclear Technology and Engineering Center (INTEC) high level wastes (HLW) is complete. This phase of the CVS addressed waste composition of high activity waste fractions (HAW) from the initial separations flowsheet. Updated estimates if INTEC calcined HLW compositions and of high activity waste fractions proposed to be separated from dissolved calcine were used as the waste component for this CVS phase. These wastes are of particular interest because high aluminum, calcium, zirconium, fluorine, potassium, and low iron and sodium content places them outside the vitrification experience in the Department of Energy complex. Because of the presence of calcium and fluorine, two major zirconia calcine components not addressed in Phase I, a series of scooping tests, designated Phase 2a, were performed. The results of these tests provided information on the effects of calcium and fluoride solubility and their impacts on product properties and composition boundary information for Phase 2b. Details and results of Phase 2a are reported separately. Through application of statistical techniques and the results of Phase 2a, a test matrix was defined for Phase 2b of the CVS. From this matrix, formulations were systematically selected for preparation and characterization with respect to visual and optical homogeneity, viscosity as a function of melt temperature, liquidus temperature (TL), and leaching properties based on response to the product consistency test. The results of preparing and characterizing the Phase 2b glasses are presented in this document. Based on the results, several formulations investigated have suitable properties for further development. A full analysis of the composition-product characteristic relationship of glasses being developed for immobilizing INTEC wastes will be performed at the completion of composition-property relationship phases of the CVS.

• Research Organization: Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID (US)
• Sponsoring Organization: USDOE Office of Science and Technology (OST) (EM-50) (US)
• DOE Contract Number: AC07-99ID13727
• OSTI ID: 768819
• Report Number(s): INEEL/EXT-99-01322
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ALUMINIUM
CALCINE
CALCIUM
CHEMICAL COMPOSITION
FLOWSHEET
FLUORINE
GLASS
GLASS COMPOSITIONS
HIGH ACTIVITY WASTE FRACTIONS
HIGH LEVEL WASTES
HIGH-LEVEL RADIOACTIVE WASTES
IDAHO NATIONAL ENGINEERING LABORATORY
IRON
LEACHING
POTASSIUM
RADIOACTIVE WASTE DISPOSAL
SODIUM
SOLUBILITY
VISCOSITY
VITRIFICATION
WASTE FORMS
ZIRCONIUM