American Nuclear Society
Home

Home / Publications / Journals / Nuclear Technology / Volume 33 / Number 1

Preparation and Characterization of Sintered Glass-Ceramics from Calcined Simulated High-Level Waste

E. G. Samsel, J. R. Berreth

Nuclear Technology / Volume 33 / Number 1 / April 1977 / Pages 68-75

Technical Paper / Radioactive Waste / dx.doi.org/10.13182/NT77-A31764

Simulated high-level commercial fluidized-bed calcine was treated to form sintered glass-ceramics (SGC) by sintering compacted mixtures of calcine with aluminosilicate fluxes at temperatures ranging from 965 to 1070°C. Products are resistant to impact and thermal shock and exhibit leach rates of 10−5 to 10−9 g/(cm2 day). Up to 67 wt% calcine is used, giving waste volumes as low as 0.040 m3 /MTU reprocessed. Storage centerline temperatures up to 800°C appear feasible. A conceptual process in which SGC is molded into thin-walled containers for processing and canister loading is proposed.