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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 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.

Authors:
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Publication Date:
Research Org.:
Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1398210
Report Number(s):
PNNL-SA-125402
Journal ID: ISSN 0022-3115; AF5805020
DOE Contract Number:
AC05-76RL01830
Resource Type:
Journal Article
Resource Relation:
Journal Name: Journal of Nuclear Materials; Journal Volume: 495
Country of Publication:
United States
Language:
English
Subject:
tellurite glass; strontium chloride; pyroprocessing; oxide reduction

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_1398210,
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 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.},
doi = {10.1016/j.jnucmat.2017.08.037},
journal = {Journal of Nuclear Materials},
number = ,
volume = 495,
place = {United States},
year = {Wed Nov 01 00:00:00 EDT 2017},
month = {Wed Nov 01 00:00:00 EDT 2017}
}