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Title: Waste form evaluation for RECl 3 and REO x fission products separated from used electrochemical salt

The work presented here is based off the concept that the rare earth chloride (RECl 3) fission products within the used electrorefiner (ER) salt can be selectively removed as RECl 3 (not yet demonstrated) or precipitated out as a mixture of REOCl and REO x through oxygen sparging (has been demonstrated). This paper presents data showing the feasibility of immobilizing a mixture of RECl 3s at 10 mass% into a 78%TeO 2-22%PbO glass while also showing that this same mixture of RECl 3s can be oxidized to REOCl at 300 °C and then to REO x by 1200 °C, evolving Cl 2(g). When the REO x mixture is heated at temperatures >1200 °C, the ratios of REO xs change. The mixture of REO x was then immobilized in a lanthanide borosilicate (LABS) glass at a high loading of 60 mass%. Both the 78%TeO 2-22%PbO glass and LABS glass systems show good chemical durability. In conclusion, the advantages and disadvantages of tellurite and LABS glasses are compared.
Authors:
ORCiD logo [1] ;  [2] ;  [1] ;  [1] ;  [1] ;  [1]
  1. Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
  2. Energy Northwest, Richland, WA (United States)
Publication Date:
Report Number(s):
PNNL-SA-124232
Journal ID: ISSN 0149-1970; PII: S0149197017302226
Grant/Contract Number:
AC05-76RL01830
Type:
Accepted Manuscript
Journal Name:
Progress in Nuclear Energy
Additional Journal Information:
Journal Volume: 104; Journal ID: ISSN 0149-1970
Publisher:
Elsevier
Research Org:
Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Sponsoring Org:
USDOE Office of Nuclear Energy (NE)
Country of Publication:
United States
Language:
English
Subject:
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; Electrorefiner; Tellurite glass; LABS glass
OSTI Identifier:
1395356

Riley, Brian J., Pierce, David A., Crum, Jarrod V., Williams, Benjamin D., Snyder, Michelle M. V., and Peterson, Jacob A.. Waste form evaluation for RECl3 and REOx fission products separated from used electrochemical salt. United States: N. p., Web. doi:10.1016/J.PNUCENE.2017.09.005.
Riley, Brian J., Pierce, David A., Crum, Jarrod V., Williams, Benjamin D., Snyder, Michelle M. V., & Peterson, Jacob A.. Waste form evaluation for RECl3 and REOx fission products separated from used electrochemical salt. United States. doi:10.1016/J.PNUCENE.2017.09.005.
Riley, Brian J., Pierce, David A., Crum, Jarrod V., Williams, Benjamin D., Snyder, Michelle M. V., and Peterson, Jacob A.. 2017. "Waste form evaluation for RECl3 and REOx fission products separated from used electrochemical salt". United States. doi:10.1016/J.PNUCENE.2017.09.005. https://www.osti.gov/servlets/purl/1395356.
@article{osti_1395356,
title = {Waste form evaluation for RECl3 and REOx fission products separated from used electrochemical salt},
author = {Riley, Brian J. and Pierce, David A. and Crum, Jarrod V. and Williams, Benjamin D. and Snyder, Michelle M. V. and Peterson, Jacob A.},
abstractNote = {The work presented here is based off the concept that the rare earth chloride (RECl3) fission products within the used electrorefiner (ER) salt can be selectively removed as RECl3 (not yet demonstrated) or precipitated out as a mixture of REOCl and REOx through oxygen sparging (has been demonstrated). This paper presents data showing the feasibility of immobilizing a mixture of RECl3s at 10 mass% into a 78%TeO2-22%PbO glass while also showing that this same mixture of RECl3s can be oxidized to REOCl at 300 °C and then to REOx by 1200 °C, evolving Cl2(g). When the REOx mixture is heated at temperatures >1200 °C, the ratios of REOxs change. The mixture of REOx was then immobilized in a lanthanide borosilicate (LABS) glass at a high loading of 60 mass%. Both the 78%TeO2-22%PbO glass and LABS glass systems show good chemical durability. In conclusion, the advantages and disadvantages of tellurite and LABS glasses are compared.},
doi = {10.1016/J.PNUCENE.2017.09.005},
journal = {Progress in Nuclear Energy},
number = ,
volume = 104,
place = {United States},
year = {2017},
month = {9}
}