Waste form evaluation for RECl3 and REOx fission products separated from used electrochemical salt

Riley, Brian J.; Pierce, David A.; Crum, Jarrod V.; Williams, Benjamin D.; Snyder, Michelle M. V.; Peterson, Jacob A.

doi:10.1016/J.PNUCENE.2017.09.005

Title: Waste form evaluation for RECl₃ and REO_x fission products separated from used electrochemical salt

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Abstract

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 REO_x 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 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%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.

Authors:

^[1]; Pierce, David A. ^[2]; Crum, Jarrod V. ^[1]; Williams, Benjamin D. ^[1]; Snyder, Michelle M. V. ^[1]; Peterson, Jacob A. ^[1]

Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Energy Northwest, Richland, WA (United States)

Publication Date:: Fri Sep 22 00:00:00 EDT 2017

Research Org.:: Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

Sponsoring Org.:: USDOE Office of Nuclear Energy (NE)

OSTI Identifier:: 1395356

Alternate Identifier(s):: OSTI ID: 1549224

Report Number(s):: PNNL-SA-124232
Journal ID: ISSN 0149-1970; PII: S0149197017302226

Grant/Contract Number:: AC05-76RL01830

Resource Type:: Journal Article: Accepted Manuscript

Journal Name:: Progress in Nuclear Energy

Additional Journal Information:: Journal Volume: 104; Journal ID: ISSN 0149-1970

Publisher:: Elsevier

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

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                    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., 2017. 
        Web.  doi:10.1016/J.PNUCENE.2017.09.005.

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                    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.  https://doi.org/10.1016/J.PNUCENE.2017.09.005

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                    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.  https://doi.org/10.1016/J.PNUCENE.2017.09.005.  https://www.osti.gov/servlets/purl/1395356.

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@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},

  url          = {https://www.osti.gov/biblio/1395356},
  journal      = {Progress in Nuclear Energy},

  issn         = {0149-1970},

  number       = ,

  volume       = 104,

  place        = {United States},

  year         = {Fri Sep 22 00:00:00 EDT 2017},

  month        = {Fri Sep 22 00:00:00 EDT 2017}

}

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Title: Waste form evaluation for RECl3 and REOx fission products separated from used electrochemical salt

Abstract

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Title: Waste form evaluation for RECl₃ and REO_x fission products separated from used electrochemical salt