September 20, 2023
Journal Article

Formulation and Testing of a High-Tin Borosilicate Nuclear Waste Glass for In-Can Melting

Abstract

Borosilicate waste glasses were successfully developed to immobilize two high-level waste raffinate streams via an in-can melter process with an Inconel 601 canister at 1050 °C. Measured viscosity and crystallinity thermal profiles were within the targeted processing constraints for the in-can melter process. Measured chemical durability of the glass by ASTM C1285–21 (Method A), ranged from normalized loss of boron, NL(B) = 1.44 – 2.65 g·m-2, and NL(B) decreased with increased waste loading, accompanied by increased SnO2 crystallinity. Measured corrosion of the in-can melter canister by a glass melt showed that Inconel 601 performed well at 1100 °C for up to 500 hr. Resistance polarization measurements versus time revealed that Inconel 601 corrosion rates in (and by) glass melts decreased from an initial rate of 63 mm·y-1 down to 10.2 mm·y-1 after 137 h with increased duration, which was attributed to formation of an oxide passivation layer (mainly Cr2O3) at the alloy-glass interface.

Published: September 20, 2023

Citation

Crum J.V., J.D. Vienna, B.J. Riley, J.A. Silverstein, R.M. Kissinger, J.J. Neeway, and J.L. George, et al. 2023. Formulation and Testing of a High-Tin Borosilicate Nuclear Waste Glass for In-Can Melting. Journal of Nuclear Materials 585. PNNL-SA-182284. doi:10.1016/j.jnucmat.2023.154643

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