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Journal ArticleDOI

Clean Up of the Purex Process TBP Solvent by Macroreticular Ion Exchange Resin

Μ. Κ. Rahman
- 01 Feb 1975 - 
- Vol. 22, pp 53-58
TLDR
In this paper, the possibility of using macroreticular ion exchange resins A-26 and A-29 for cleaning the used purex process solvent has been investigated, and the distribution co-efficients for Ru-Rh and Zr-Nb have been determined using the solution under three different conditions, i.e., active solution of pu ~ 0.5 as supplied, active solution washed with 1 M Na2C03 accompanied by rise in pu to 5.0; Washed solution equilibrated with IN. HN03 thus bringing down the pa to
Abstract
The possibility of using macroreticular ion-exchange resin A-26 and A-29 for cleaning the used purex process solvent has been investigated. The distribution co-efficients for Ru-Rh and Zr-Nb have been determined using the solution under three different conditions—active solution of pu ~ 0.5 as supplied, active solution washed with 1 M Na2C03 accompanied by rise in pu to — 5.0; Washed solution equilibrated with IN. HN03 thus bringing down the pa to ~0.5. The effects of temperature and particle size of the resins, on the distribution values have been evaluated. There is indication that distribution is preceded at least partly by decomposition of Ru-complex at higher pn and elevated temperature. Use of two different Purex process solutions revealed that distribution ratios are also dependent on the background history of the used solvents.

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Journal ArticleDOI

STUDIES ON THE UPTAKE OF Th(IV), U(VI) AND Pu(IV) ON DOWEX 50WX8 RESIN FROM TBP-SHELL SOL-T MIXTURES

TL;DR: In this article, a batch equilibration study has been carried out to understand the uptake of Th(IV), U(VI) and Pu(IV) on a conventional gel type cation exchange resin, Dowex 50WX8, from TBP-shell Sol-T mixtures containing different amounts of nitric acid.
Journal ArticleDOI

Ion exchange studies for the removal of plutonium and americium from organic liquid scintillator waste solution

TL;DR: In this article, an ion exchange study was carried out using simulated alpha active organic liquid scintillator and ethyl alcohol waste solutions containing Pu and Am using different resins, including Macroporous bifunctional phosphinic acid (MPBPA) and Amberlite IR-120.

Ion Exchange in Nuclear Fuel Reprocessing : Zirconium Phosphate Materials for the Separation of Trivalent Actinides and Lanthanides

TL;DR: In this paper, the authors present a list of original publications and their corresponding abstracts, including acknowledgements, references, and abbreviations of the original publications, and references.