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Title: Assessment of lead tellurite glass for immobilizing electrochemical salt wastes from used nuclear fuel reprocessing

Abstract

This paper provides an overview of research evaluating the use of lead tellurite glass as a waste form for salt wastes from electrochemical reprocessing of used nuclear fuel. The efficacy of using lead tellurite glass to immobilize three different salt compositions was evaluated: a LiCl-Li2O oxide reduction salt containing fission products from oxide fuel, a LiCl-KCl eutectic salt containing fission products from metallic fuel, and SrCl2. Physical and chemical properties of glasses made with these salts were characterized with X-ray diffraction, bulk density measurements, differential thermal analysis, chemical durability tests, scanning and transmission electron microscopies, and energy-dispersive X-ray spectroscopy. These glasses were found to accommodate high salt concentrations and have high densities, but further development is needed to improve chemical durability. (C) 2017 Published by Elsevier B.V.

Authors:
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Publication Date:
Research Org.:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1411170
DOE Contract Number:  
AC02-06CH11357
Resource Type:
Journal Article
Resource Relation:
Journal Name: Journal of Nuclear Materials; Journal Volume: 495; Journal Issue: C
Country of Publication:
United States
Language:
English

Citation Formats

Riley, Brian J., Kroll, Jared O., Peterson, Jacob A., Pierce, David A., Ebert, William L., Williams, Benjamin D., Snyder, Michelle M. V., Frank, Steven M., George, Jaime L., and Kruska, Karen. Assessment of lead tellurite glass for immobilizing electrochemical salt wastes from used nuclear fuel reprocessing. United States: N. p., 2017. Web. doi:10.1016/j.jnucmat.2017.08.037.
Riley, Brian J., Kroll, Jared O., Peterson, Jacob A., Pierce, David A., Ebert, William L., Williams, Benjamin D., Snyder, Michelle M. V., Frank, Steven M., George, Jaime L., & Kruska, Karen. Assessment of lead tellurite glass for immobilizing electrochemical salt wastes from used nuclear fuel reprocessing. United States. doi:10.1016/j.jnucmat.2017.08.037.
Riley, Brian J., Kroll, Jared O., Peterson, Jacob A., Pierce, David A., Ebert, William L., Williams, Benjamin D., Snyder, Michelle M. V., Frank, Steven M., George, Jaime L., and Kruska, Karen. Wed . "Assessment of lead tellurite glass for immobilizing electrochemical salt wastes from used nuclear fuel reprocessing". United States. doi:10.1016/j.jnucmat.2017.08.037.
@article{osti_1411170,
title = {Assessment of lead tellurite glass for immobilizing electrochemical salt wastes from used nuclear fuel reprocessing},
author = {Riley, Brian J. and Kroll, Jared O. and Peterson, Jacob A. and Pierce, David A. and Ebert, William L. and Williams, Benjamin D. and Snyder, Michelle M. V. and Frank, Steven M. and George, Jaime L. and Kruska, Karen},
abstractNote = {This paper provides an overview of research evaluating the use of lead tellurite glass as a waste form for salt wastes from electrochemical reprocessing of used nuclear fuel. The efficacy of using lead tellurite glass to immobilize three different salt compositions was evaluated: a LiCl-Li2O oxide reduction salt containing fission products from oxide fuel, a LiCl-KCl eutectic salt containing fission products from metallic fuel, and SrCl2. Physical and chemical properties of glasses made with these salts were characterized with X-ray diffraction, bulk density measurements, differential thermal analysis, chemical durability tests, scanning and transmission electron microscopies, and energy-dispersive X-ray spectroscopy. These glasses were found to accommodate high salt concentrations and have high densities, but further development is needed to improve chemical durability. (C) 2017 Published by Elsevier B.V.},
doi = {10.1016/j.jnucmat.2017.08.037},
journal = {Journal of Nuclear Materials},
number = C,
volume = 495,
place = {United States},
year = {Wed Nov 01 00:00:00 EDT 2017},
month = {Wed Nov 01 00:00:00 EDT 2017}
}