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Title: Characterization of Spent Purolite A530E Resin with Implications for Long-Term Radioactive Contaminant Removal

Abstract

Direct removal of pertechnetate anion (TcO4-) from the subsurface contaminated plumes at legacy nuclear weapons production sites, is effective remediation strategy to prevent their spread to adjacent aquifers but is also challenging because TcO4- is a trace component of the contaminated groundwater typically containing large access of other anionic constituents, such nitrate, sulfate, chloride and others. It can be achieved through ion exchange treatment using Purolite A530E resin which to date however has only been evaluated under laboratory conditions and many questions regarding its long-term operational performance remain. To address this need, here we report comprehensive characterization of the spent Purolite A530E resin which processed over 5.38x109 L of contaminated groundwater and successfully removed about 3.78 Ci of Tc-99 during four years of operation at the 200 West Pump & Treat facility at the US DOE Hanford site. This Tc-99 loading constitutes however only about 0.034% of the theoretical capacity of the resin which retained significant amounts of sulfate. Among other radioactive contaminants, small quantities of U-238, Co-60, and I-129 were retained by the resin. The total loading of iodine (combined 1-127 and I-129) on the spent resin exceeded that of Tc-99. To elucidate the mechanism of iodine retention, ionmore » exchange behavior of iodide and iodate was investigated. Purolite A530E resin exhibited highly efficient uptake of iodide and only moderate affinity for iodate in accord with their Gibbs energy of hydration. Sorption isotherms for both anions obeyed Freundlich model.« less

Authors:
ORCiD logo [1];  [1]; ORCiD logo [1];  [1];  [1];  [2];  [1]
  1. BATTELLE (PACIFIC NW LAB)
  2. CH2M HILL PLATEAU REMEDIATION COMPANY
Publication Date:
Research Org.:
Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1661883
Report Number(s):
PNNL-SA-148120
DOE Contract Number:  
AC05-76RL01830
Resource Type:
Journal Article
Journal Name:
Journal of Environmental Chemical Engineering
Additional Journal Information:
Journal Volume: 8; Journal Issue: 5
Country of Publication:
United States
Language:
English

Citation Formats

Levitskaia, Tatiana G., Campbell, Emily L., Hall, Gabriel B., Chatterjee, Sayandev, Boglaienko, Daria, Carlson, Mark A., and Reilly, Dallas D. Characterization of Spent Purolite A530E Resin with Implications for Long-Term Radioactive Contaminant Removal. United States: N. p., 2020. Web. doi:10.1016/j.jece.2020.104155.
Levitskaia, Tatiana G., Campbell, Emily L., Hall, Gabriel B., Chatterjee, Sayandev, Boglaienko, Daria, Carlson, Mark A., & Reilly, Dallas D. Characterization of Spent Purolite A530E Resin with Implications for Long-Term Radioactive Contaminant Removal. United States. doi:10.1016/j.jece.2020.104155.
Levitskaia, Tatiana G., Campbell, Emily L., Hall, Gabriel B., Chatterjee, Sayandev, Boglaienko, Daria, Carlson, Mark A., and Reilly, Dallas D. Thu . "Characterization of Spent Purolite A530E Resin with Implications for Long-Term Radioactive Contaminant Removal". United States. doi:10.1016/j.jece.2020.104155.
@article{osti_1661883,
title = {Characterization of Spent Purolite A530E Resin with Implications for Long-Term Radioactive Contaminant Removal},
author = {Levitskaia, Tatiana G. and Campbell, Emily L. and Hall, Gabriel B. and Chatterjee, Sayandev and Boglaienko, Daria and Carlson, Mark A. and Reilly, Dallas D.},
abstractNote = {Direct removal of pertechnetate anion (TcO4-) from the subsurface contaminated plumes at legacy nuclear weapons production sites, is effective remediation strategy to prevent their spread to adjacent aquifers but is also challenging because TcO4- is a trace component of the contaminated groundwater typically containing large access of other anionic constituents, such nitrate, sulfate, chloride and others. It can be achieved through ion exchange treatment using Purolite A530E resin which to date however has only been evaluated under laboratory conditions and many questions regarding its long-term operational performance remain. To address this need, here we report comprehensive characterization of the spent Purolite A530E resin which processed over 5.38x109 L of contaminated groundwater and successfully removed about 3.78 Ci of Tc-99 during four years of operation at the 200 West Pump & Treat facility at the US DOE Hanford site. This Tc-99 loading constitutes however only about 0.034% of the theoretical capacity of the resin which retained significant amounts of sulfate. Among other radioactive contaminants, small quantities of U-238, Co-60, and I-129 were retained by the resin. The total loading of iodine (combined 1-127 and I-129) on the spent resin exceeded that of Tc-99. To elucidate the mechanism of iodine retention, ion exchange behavior of iodide and iodate was investigated. Purolite A530E resin exhibited highly efficient uptake of iodide and only moderate affinity for iodate in accord with their Gibbs energy of hydration. Sorption isotherms for both anions obeyed Freundlich model.},
doi = {10.1016/j.jece.2020.104155},
journal = {Journal of Environmental Chemical Engineering},
number = 5,
volume = 8,
place = {United States},
year = {2020},
month = {10}
}