Capture of volatile RuO4 from oxidized simulated used nuclear fuel solutions

Jeffrey D. Einkauf, Jennifer M. Pyles, Marcy E. Lamb, Luke R. Sadergaski, Harry M. Meyer, Lætitia H. Delmau, Bruce A. Moyer, Jonathan D. Burns

Research output: Contribution to journalArticlepeer-review

Abstract

Ruthenium is a challenging fission product in used nuclear fuel (UNF) reprocessing due to its complex redox chemistry, variable speciation in nitric acid, partial extractability, and volatility. This work presents a strategy for Ru removal based on the volatilization of RuO4 using the strong oxidant sodium bismuthate, followed by RuO2 deposition onto various substrates. Among the materials tested, polymer-based substrates such as polyolefin wax film (Parafilm®), exhibited superior performance, achieving up to near-quantitative Ru removal from solution. After dissolution of the substrate, 99.6 % of the Ru was recovered as RuO2. The deposition mechanism onto the polyolefin wax film involves both physisorption and chemical reaction through oxidative cleavage of olefinic bonds within the polymer. In contrast, on inorganic substrates such as Al foil, RuO4 undergoes incomplete surface adsorption and reduction, as confirmed by FTIR and XPS analyses. This approach remains effective under conditions of simulated oxidation of UNF solutions, selectively removing Ru while leaving other fission products in solution. Capture of RuO4 offers a practical and efficient strategy for ruthenium decontamination and recovery, offering a route for integration into existing UNF reprocessing flowsheets to enhance overall process safety and performance.

Original languageEnglish
Article number135576
JournalSeparation and Purification Technology
Volume382
DOIs
StatePublished - Feb 26 2026

Funding

Research supported by Converting UNF Radioisotopes Into Energy (CURIE) Program, Advanced Research Projects Agency – Energy (ARPA-E), US Department of Energy, Grant # DE-AR0001689 (P.I. Burns). ☆ This submitted manuscript has been authored by UT-Battelle, LLC, under contract DE-AC05-00OR22725 in collaboration with the University of Alabama at Birmingham under Award Number DE-AR0001689 with the U.S. Department of Energy. The United States Government retains and the publisher, by accepting the article for publication, acknowledges that the United States Government retains a non-exclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for the United States Government purposes. The Department of Energy will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doe-public-access-plan). ☆☆☆ The information, data, or work presented herein was funded in part by the Advanced Research Projects Agency-Energy (ARPA-E), U.S. Department of Energy, under contract DE-AC05-00OR22725 and Award Number DE-AR0001689. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.

Keywords

  • Ruthenium
  • Ruthenium tetroxide
  • Sodium bismuthate
  • Used nuclear fuel

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