Zirconium and technetium recovery and partitioning in the presence of actinides in modified Purex process for ATW program. Final report

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The modified Purex process flowsheet is based on combination of all irradiated materials, their joint dissolution and reprocessing as a NPP spent fuel solution with abnormal Pu content after addition of recycled depleted U concentrate. Some groups of long-lived radionuclides could be completely recovered and localized at the stage of extraction reprocessing using 30% TBP. Studies were conducted for 10 y to develop the process for recovery, concentration, and localization of U, Pu, Np, Tc, and Zr within 1st extraction cycle. Actinides are recovered from high-level raffinate of this cycle after evaporation and feed adjustment. Results in this report show ... continued below

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33 p.

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Dzekun, E.G.; Fedorov, Y.S.; Galkin, B.Y.; Lyubtsev, R.I.; Mashkin, A.N.; Mishin, E.N. et al. December 31, 1994.

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Description

The modified Purex process flowsheet is based on combination of all irradiated materials, their joint dissolution and reprocessing as a NPP spent fuel solution with abnormal Pu content after addition of recycled depleted U concentrate. Some groups of long-lived radionuclides could be completely recovered and localized at the stage of extraction reprocessing using 30% TBP. Studies were conducted for 10 y to develop the process for recovery, concentration, and localization of U, Pu, Np, Tc, and Zr within 1st extraction cycle. Actinides are recovered from high-level raffinate of this cycle after evaporation and feed adjustment. Results in this report show that combined deep recovery of several elements from highly irradiated materials by TBP extraction, for further transmutation, is possible. Selective stripping of Zr from solvent phase containing U, Pu, Np, and Tc is quite effective. Development of the modified Purex process is not complete; main problem to be solved should be oxide separation from the loop and permissible storage duration before reprocessing and reuse in the loop.

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33 p.

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INIS; OSTI as DE97002419

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  • Other Information: PBD: 1994

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  • Other: DE97002419
  • Report No.: LA-SUB--95-81
  • Grant Number: W-7405-ENG-36
  • DOI: 10.2172/432445 | External Link
  • Office of Scientific & Technical Information Report Number: 432445
  • Archival Resource Key: ark:/67531/metadc688446

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  • December 31, 1994

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  • July 25, 2015, 2:20 a.m.

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  • July 28, 2016, 7:29 p.m.

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Dzekun, E.G.; Fedorov, Y.S.; Galkin, B.Y.; Lyubtsev, R.I.; Mashkin, A.N.; Mishin, E.N. et al. Zirconium and technetium recovery and partitioning in the presence of actinides in modified Purex process for ATW program. Final report, report, December 31, 1994; New Mexico. (digital.library.unt.edu/ark:/67531/metadc688446/: accessed September 22, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.