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Title: Efficacy of a Solution-Based Approach for Making Sodalite Waste Forms for an Oxide Reduction Salt Utilized in the Reprocessing of Used Uranium Oxide Fuel

Abstract

This paper describes various approaches for making sodalite with a LiCl-Li2O oxide reduction salt used to recover uranium from used oxide fuel. The approaches include sol-gel and solution-based synthesis processes. As-made products were mixed with 5 and 10 mass% of a Na2O-B2O3-SiO2 glass binder and these, along with product without a binder, were heated using either a cold-press-and-sinter method or hot uniaxial pressing. The results demonstrate the limitation of sodalite yield due to the fast intermediate reactions between Na+ and Cl- to form halite in solution and Li2O and SiO2 to form lithium silicates (e.g., Li2SiO3 or Li2Si2O5) in the calcined and sintered pellets. The results show that pellets can be made with high sodalite fractions (~92 mass%) and low porosities using a solution-based approach and this LiCl-Li2O salt.

Authors:
; ; ; ;
Publication Date:
Research Org.:
Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1208760
Report Number(s):
PNNL-SA-103835
AF5805010
DOE Contract Number:  
AC05-76RL01830
Resource Type:
Journal Article
Journal Name:
Journal of Nuclear Materials, 459:313-322
Additional Journal Information:
Journal Name: Journal of Nuclear Materials, 459:313-322
Country of Publication:
United States
Language:
English
Subject:
sodalite; electrochemical; lithium chloride; oxide reduction

Citation Formats

Riley, Brian J., Pierce, David A., Frank, Steven M., Matyas, Josef, and Burns, Carolyn A. Efficacy of a Solution-Based Approach for Making Sodalite Waste Forms for an Oxide Reduction Salt Utilized in the Reprocessing of Used Uranium Oxide Fuel. United States: N. p., 2015. Web. doi:10.1016/j.jnucmat.2014.09.042.
Riley, Brian J., Pierce, David A., Frank, Steven M., Matyas, Josef, & Burns, Carolyn A. Efficacy of a Solution-Based Approach for Making Sodalite Waste Forms for an Oxide Reduction Salt Utilized in the Reprocessing of Used Uranium Oxide Fuel. United States. https://doi.org/10.1016/j.jnucmat.2014.09.042
Riley, Brian J., Pierce, David A., Frank, Steven M., Matyas, Josef, and Burns, Carolyn A. 2015. "Efficacy of a Solution-Based Approach for Making Sodalite Waste Forms for an Oxide Reduction Salt Utilized in the Reprocessing of Used Uranium Oxide Fuel". United States. https://doi.org/10.1016/j.jnucmat.2014.09.042.
@article{osti_1208760,
title = {Efficacy of a Solution-Based Approach for Making Sodalite Waste Forms for an Oxide Reduction Salt Utilized in the Reprocessing of Used Uranium Oxide Fuel},
author = {Riley, Brian J. and Pierce, David A. and Frank, Steven M. and Matyas, Josef and Burns, Carolyn A.},
abstractNote = {This paper describes various approaches for making sodalite with a LiCl-Li2O oxide reduction salt used to recover uranium from used oxide fuel. The approaches include sol-gel and solution-based synthesis processes. As-made products were mixed with 5 and 10 mass% of a Na2O-B2O3-SiO2 glass binder and these, along with product without a binder, were heated using either a cold-press-and-sinter method or hot uniaxial pressing. The results demonstrate the limitation of sodalite yield due to the fast intermediate reactions between Na+ and Cl- to form halite in solution and Li2O and SiO2 to form lithium silicates (e.g., Li2SiO3 or Li2Si2O5) in the calcined and sintered pellets. The results show that pellets can be made with high sodalite fractions (~92 mass%) and low porosities using a solution-based approach and this LiCl-Li2O salt.},
doi = {10.1016/j.jnucmat.2014.09.042},
url = {https://www.osti.gov/biblio/1208760}, journal = {Journal of Nuclear Materials, 459:313-322},
number = ,
volume = ,
place = {United States},
year = {Wed Apr 01 00:00:00 EDT 2015},
month = {Wed Apr 01 00:00:00 EDT 2015}
}