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Comparison of the performance of solvent wash reagents used for the primary cleanup of degraded PUREX solvent

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Published/Copyright: November 23, 2022
Radiochimica Acta
From the journal Radiochimica Acta Volume 111 Issue 1

Abstract

The effectiveness of the solvent wash reagents such as sodium carbonate and hydrazine carbonate were compared using the lean solvent obtained during reprocessing of high plutonium content fast reactor spent nuclear fuel. The concentrations of the reagents were optimized based on the removal of retained metal ions from the lean solvent and 1.5 M hydrazine carbonate was found to be optimal and superior to sodium carbonate to be adopted as the reagent for primary cleanup of the spent solvent. Both the reagents were found to possess excellent room temperature stability and their performance was not affected upon gamma irradiation which was assessed in terms of capacity to remove di-butyl phosphate from degraded TBP/n-DD system.

Keywords: gamma irradiation; lean organic; plutonium retention; sodium carbonate wash
Corresponding author: Konda Athmaram Venkatesan, Reprocessing Group, IGCAR, Kalpakkam, India; and Homi Bhabha National Institute, Mumbai 400 094, India, E-mail:

  1. Author contributions: All the authors have accepted responsibility for the entire content of this submitted manuscript and approved submission.

  2. Research funding: None declared.

  3. Conflict of interest statement: The authors declare no conflicts of interest regarding this article.

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Received: 2022-08-02
Accepted: 2022-10-18
Published Online: 2022-11-23
Published in Print: 2023-01-27

© 2022 Walter de Gruyter GmbH, Berlin/Boston

Articles in the same Issue

  1. Frontmatter
  2. Review
  3. Progress in solid state and coordination chemistry of actinides in China
  4. Original Papers
  5. Np(V) dicyanamide complexes with electroneutral N-donor ligands
  6. Comparison of the performance of solvent wash reagents used for the primary cleanup of degraded PUREX solvent
  7. 1-aza-18-crown-6 ether tailored graphene oxide for Cs(I) removal from wastewater
  8. Evaluation of nuclear data analysis techniques for volume fraction prediction in the flow meter
https://doi.org/10.1515/ract-2022-0079
Keywords for this article
gamma irradiation; lean organic; plutonium retention; sodium carbonate wash

Articles in the same Issue

  1. Frontmatter
  2. Review
  3. Progress in solid state and coordination chemistry of actinides in China
  4. Original Papers
  5. Np(V) dicyanamide complexes with electroneutral N-donor ligands
  6. Comparison of the performance of solvent wash reagents used for the primary cleanup of degraded PUREX solvent
  7. 1-aza-18-crown-6 ether tailored graphene oxide for Cs(I) removal from wastewater
  8. Evaluation of nuclear data analysis techniques for volume fraction prediction in the flow meter
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