TRUEX process applied to radioactive Idaho Chemical Processing Plant high-level waste calcine

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Equal volume batch contact experiments were performed with dissolved, radioactive high-level waste (HLW) calcine and the TRansUranic EXtraction (TRUEX) process solvent. Extraction, scrub, and strip distribution coefficients (D) were obtained for the transuranic (TRU) elements in order to evaluate the efficiency of the TRUEX process in treating this waste. The extraction, scrub, and strip behavior of other elements, such as chromium, zirconium, and technetium, was also observed. A TRU alpha decontamination factor of >10,000 was achieved; after three extraction batch contacts TRU alpha activity was reduced from 1,420 nCi/g to 0.02 nCi/g. Dilute nitric acid was used to scrub extracted ... continued below

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8 p.

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Brewer, K.N.; Herbst, R.S.; Law, J.D.; Todd, T.A. & Olson, A.L. May 1, 1996.

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Description

Equal volume batch contact experiments were performed with dissolved, radioactive high-level waste (HLW) calcine and the TRansUranic EXtraction (TRUEX) process solvent. Extraction, scrub, and strip distribution coefficients (D) were obtained for the transuranic (TRU) elements in order to evaluate the efficiency of the TRUEX process in treating this waste. The extraction, scrub, and strip behavior of other elements, such as chromium, zirconium, and technetium, was also observed. A TRU alpha decontamination factor of >10,000 was achieved; after three extraction batch contacts TRU alpha activity was reduced from 1,420 nCi/g to 0.02 nCi/g. Dilute nitric acid was used to scrub extracted acid, zirconium, and iron from the solvent prior to stripping. Dilute 1-hydroxyethane, 1-1, diphosphonic acid (HEDPA) was used as a gross TRU stripping reagent to recover the extracted TRUs. Data from these batch contact experiments were used to develop a counter-current flowsheet for TRU removal using the Generic TRUEX Model (GTM). Process improvements and optimizations of the flowsheet have been evaluated using a non-radioactive dissolved calcine simulant spiked with tracers to obtain additional distribution coefficient data. These data were used in the GTM to refine the flowsheet. The flowsheet was then evaluated using a counter-current 5.5 cm centrifugal contactor pilot plant with a non-radioactive dissolved calcine simulant. The experiments involving radioactive waste provided crucial data for developing a baseline TRUEX process flowsheet which can effectively separate TRU components from ICPP high-level waste.

Physical Description

8 p.

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INIS; OSTI as DE96010437

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  • SPECTRUM `96: international conference on nuclear and hazardous waste management, Seattle, WA (United States), 18-23 Aug 1996

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  • Other: DE96010437
  • Report No.: INEL--95/00603
  • Report No.: CONF-960804--26
  • Grant Number: AC07-76ID01570
  • Office of Scientific & Technical Information Report Number: 251604
  • Archival Resource Key: ark:/67531/metadc665893

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

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  • May 1, 1996

Added to The UNT Digital Library

  • June 29, 2015, 9:42 p.m.

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  • April 25, 2016, 12:02 p.m.

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Brewer, K.N.; Herbst, R.S.; Law, J.D.; Todd, T.A. & Olson, A.L. TRUEX process applied to radioactive Idaho Chemical Processing Plant high-level waste calcine, article, May 1, 1996; Idaho Falls, Idaho. (digital.library.unt.edu/ark:/67531/metadc665893/: accessed July 22, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.