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Title: Alternative Electrochemical Salt Waste Forms, Summary of FY11-FY12 Results

Abstract

The Fuel Cycle Research and Development Program, sponsored by the U.S. Department of Energy Office of Nuclear Energy, is currently investigating alternative waste forms for wastes generated from nuclear fuel processing. One such waste results from an electrochemical separations process, called the “Echem” process. The Echem process utilizes a molten KCl-LiCl salt to dissolve the fuel. This process results in a spent salt containing alkali, alkaline earth, lanthanide halides and small quantities of actinide halides, where the primary halide is chloride with a minor iodide fraction. Pacific Northwest National Laboratory (PNNL) is concurrently investigating two candidate waste forms for the Echem spent-salt: high-halide minerals (i.e., sodalite and cancrinite) and tellurite (TeO2)-based glasses. Both of these candidates showed promise in fiscal year (FY) 2009 and FY2010 with a simplified nonradioactive simulant of the Echem waste. Further testing was performed on these waste forms in FY2011 and FY2012 to assess the possibility of their use in a sustainable fuel cycle. This report summarizes the combined results from FY2011 and FY2012 efforts.

Authors:
 [1];  [1];  [1];  [1];  [1];  [1];  [1];  [1];  [1];  [1];  [1];  [1]
  1. Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Publication Date:
Research Org.:
Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1176854
Report Number(s):
PNNL-22034 Rev. 1
AF5805010
DOE Contract Number:  
AC05-76RL01830
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; sodalite; electrochemical; tellurite glass; waste form

Citation Formats

Riley, Brian J., Mccloy, John S., Crum, Jarrod V., Lepry, William C., Rodriguez, Carmen P., Windisch, Charles F., Matyas, Josef, Westman, Matthew P., Rieck, Bennett T., Lang, Jesse B., Olszta, Matthew J., and Pierce, David A. Alternative Electrochemical Salt Waste Forms, Summary of FY11-FY12 Results. United States: N. p., 2014. Web. doi:10.2172/1176854.
Riley, Brian J., Mccloy, John S., Crum, Jarrod V., Lepry, William C., Rodriguez, Carmen P., Windisch, Charles F., Matyas, Josef, Westman, Matthew P., Rieck, Bennett T., Lang, Jesse B., Olszta, Matthew J., & Pierce, David A. Alternative Electrochemical Salt Waste Forms, Summary of FY11-FY12 Results. United States. https://doi.org/10.2172/1176854
Riley, Brian J., Mccloy, John S., Crum, Jarrod V., Lepry, William C., Rodriguez, Carmen P., Windisch, Charles F., Matyas, Josef, Westman, Matthew P., Rieck, Bennett T., Lang, Jesse B., Olszta, Matthew J., and Pierce, David A. 2014. "Alternative Electrochemical Salt Waste Forms, Summary of FY11-FY12 Results". United States. https://doi.org/10.2172/1176854. https://www.osti.gov/servlets/purl/1176854.
@article{osti_1176854,
title = {Alternative Electrochemical Salt Waste Forms, Summary of FY11-FY12 Results},
author = {Riley, Brian J. and Mccloy, John S. and Crum, Jarrod V. and Lepry, William C. and Rodriguez, Carmen P. and Windisch, Charles F. and Matyas, Josef and Westman, Matthew P. and Rieck, Bennett T. and Lang, Jesse B. and Olszta, Matthew J. and Pierce, David A.},
abstractNote = {The Fuel Cycle Research and Development Program, sponsored by the U.S. Department of Energy Office of Nuclear Energy, is currently investigating alternative waste forms for wastes generated from nuclear fuel processing. One such waste results from an electrochemical separations process, called the “Echem” process. The Echem process utilizes a molten KCl-LiCl salt to dissolve the fuel. This process results in a spent salt containing alkali, alkaline earth, lanthanide halides and small quantities of actinide halides, where the primary halide is chloride with a minor iodide fraction. Pacific Northwest National Laboratory (PNNL) is concurrently investigating two candidate waste forms for the Echem spent-salt: high-halide minerals (i.e., sodalite and cancrinite) and tellurite (TeO2)-based glasses. Both of these candidates showed promise in fiscal year (FY) 2009 and FY2010 with a simplified nonradioactive simulant of the Echem waste. Further testing was performed on these waste forms in FY2011 and FY2012 to assess the possibility of their use in a sustainable fuel cycle. This report summarizes the combined results from FY2011 and FY2012 efforts.},
doi = {10.2172/1176854},
url = {https://www.osti.gov/biblio/1176854}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Jan 17 00:00:00 EST 2014},
month = {Fri Jan 17 00:00:00 EST 2014}
}