Crystallization in simulated glasses from Hanford high-level nuclear waste composition range

Conference · Thu Apr 01 04:00:00 EST 1993

OSTI ID:10157716

Kim, Dong-Sang; Hrma, P; Smith, D E; Schweiger, M J

Glass crystallization was investigated as part of a property-composition relationship study of Hanford waste glasses. Non-radioactive glass samples were heated in a gradient furnace over a wide range of temperatures. The liquidus temperature was measured, and primary crystalline phases were determined using optical microscopy and Scanning Electron Microscopy with Energy Dispersive Spectrometry (SEM/EDS). Samples have also been heat treated according to a simulated canister centerline cooling curve. The crystalline phases in these samples have been identified by optical microscopy, SEM/EDS, and X-ray diffraction (XRD). Major components of the borosilicate glasses that were melted at approximately 1150{degrees}C were SiO{sub 2}, B{sub 2}O{sub 3}, Na{sub 2}O, Li{sub 2}O, CaO, MgO, Fe{sub 2}O{sub 3}, Al{sub 2}O{sub 3}, ZrO{sub 2}, and ``Others`` (sum of minor components). The major crystalline phases identified in this study were zircon, nepheline, calcium silicate, lithium silicate, and a range of solid solutions from clinopyroxenes, orthopyroxenes, olivines, and spiners.

• Research Organization: Pacific Northwest Lab., Richland, WA (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 10157716
• Report Number(s): PNL-SA--22303; CONF-930438--18; ON: DE93013504
• Country of Publication: United States
• Language: English

Related Subjects

052001
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
36 MATERIALS SCIENCE
360601
360602
BOROSILICATE GLASS
CRYSTALLIZATION
HANFORD RESERVATION
HIGH-LEVEL RADIOACTIVE WASTES
MELTING
OXIDES
PREPARATION AND MANUFACTURE
RADIOACTIVE WASTE PROCESSING
SIMULATION
STRUCTURE AND PHASE STUDIES
TEMPERATURE RANGE 0400-1000 K
VITRIFICATION
WASTE PROCESSING