Application of single ion activity coefficients to determine solvent extraction mechanism for components of high level nuclear waste

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The TRUEX solvent extraction process is being developed to remove and concentrate transuranic (TRU) elements from high-level and TRU radioactive wastes currently stored at US Department of Energy sites. Phosphoric acid is one of the chemical species of concern at the Hanford site where bismuth phosphate was used to recover plutonium. The mechanism of phosphoric acid extraction with TRUEX-NPH solvent at 25{degrees}C was determined by phosphoric acid distribution ratios, which were measured by using phosphoric acid radiotracer and a variety of aqueous phases containing different concentrations of nitric acid and nitrate ions. A model was developed for predicting phosphoric acid ... continued below

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18 p.

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Nunez, L. & Vandegrift, G.F. December 31, 1995.

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Description

The TRUEX solvent extraction process is being developed to remove and concentrate transuranic (TRU) elements from high-level and TRU radioactive wastes currently stored at US Department of Energy sites. Phosphoric acid is one of the chemical species of concern at the Hanford site where bismuth phosphate was used to recover plutonium. The mechanism of phosphoric acid extraction with TRUEX-NPH solvent at 25{degrees}C was determined by phosphoric acid distribution ratios, which were measured by using phosphoric acid radiotracer and a variety of aqueous phases containing different concentrations of nitric acid and nitrate ions. A model was developed for predicting phosphoric acid distribution ratios as a function of the thermodynamic activities of nitrate ion and hydrogen ion. The Generic TRUEX Model (GTM) was used to calculate these activities based on the Bromley method. The derived model supports CMPO and TBP extraction of a phosphoric acid-nitric acid complex and a CMPO-phosphoric acid complex in TRUEX-NPH solvent.

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18 p.

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INIS; OSTI as DE96004291

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  • 9. symposium on separation science and technology for energy applications, Gatlinburg, TN (United States), 22-26 Oct 1995

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  • Other: DE96004291
  • Report No.: ANL/CMT/VU--86003
  • Report No.: CONF-951057--6
  • Grant Number: W-31-109-ENG-38
  • Office of Scientific & Technical Information Report Number: 211398
  • Archival Resource Key: ark:/67531/metadc669965

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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  • December 31, 1995

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  • June 29, 2015, 9:42 p.m.

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  • Dec. 15, 2015, 6:53 p.m.

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Nunez, L. & Vandegrift, G.F. Application of single ion activity coefficients to determine solvent extraction mechanism for components of high level nuclear waste, article, December 31, 1995; Illinois. (digital.library.unt.edu/ark:/67531/metadc669965/: accessed October 21, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.