This paper provides an overview of research evaluating the use of tellurite glass as a waste form for salt wastes from electrochemical processing. The capacities to immobilize different salts were evaluated including: a LiCl-Li2O oxide reduction salt (for oxide fuel) containing fission products, a LiCl-KCl eutectic salt (for metallic fuel) containing fission products, and SrCl2. Physical and chemical properties of the glasses were characterized by using X-ray diffraction, bulk density measurements, chemical durability tests, scanning electron microscopy, and energy dispersive X-ray emission spectroscopy. These glasses were found to accommodate high concentrations of halide salts and have high densities. However, improvements are needed to meet chemical durability requirements.
Revised: September 27, 2017 |
Published: August 30, 2017
Citation
Riley B.J., J.O. Kroll, J.A. Peterson, D.A. Pierce, W.L. Ebert, B.D. Williams, and M. Snyder, et al. 2017.Assessment of lead tellurite glass for immobilizing electrochemical salt wastes from used nuclear fuel reprocessing.Journal of Nuclear Materials 495.PNNL-SA-125402.doi:10.1016/j.jnucmat.2017.08.037