TRUEX partitioning from radioactive ICPP sodium bearing waste

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Description

The Idaho Chemical Processing Plant (ICPP) located at the Idaho National Engineering Laboratory in Southeast Idaho is currently evaluating several treatment technologies applicable to waste streams generated over several decades of-nuclear fuel reprocessing. Liquid sodium bearing waste (SBW), generated primarily during decontamination activities, is one of the waste streams of interest. The TRansUranic EXtraction (TRUEX) process developed at Argonne National Laboratory is currently being evaluated to separate the actinides from SBW. On a mass basis, the amount of the radioactive species in SBW are low relative to inert matrix components. Thus, the advantage of separations is a dramatic decrease in ... continued below

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23 p.

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Herbst, R. S.; Brewer, K. N.; Tranter, T. J. & Todd, T. A. March 1995.

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Description

The Idaho Chemical Processing Plant (ICPP) located at the Idaho National Engineering Laboratory in Southeast Idaho is currently evaluating several treatment technologies applicable to waste streams generated over several decades of-nuclear fuel reprocessing. Liquid sodium bearing waste (SBW), generated primarily during decontamination activities, is one of the waste streams of interest. The TRansUranic EXtraction (TRUEX) process developed at Argonne National Laboratory is currently being evaluated to separate the actinides from SBW. On a mass basis, the amount of the radioactive species in SBW are low relative to inert matrix components. Thus, the advantage of separations is a dramatic decrease in resulting volumes of high activity waste (HAW) which must be dispositioned. Numerous studies conducted at the ICPP indicate the applicability of the TRUEX process has been demonstrated; however, these studies relied on a simulated SBW surrogate for the real waste. Consequently, a series of batch contacts were performed on samples of radioactive ICPP SBW taken from tank WM-185 to verify that actual waste would behave similarly to the simulated waste. The test results with SBW from tank WM-185 indicate the TRUEX solvent effectively extracts the actinides from the samples of actual waste. Gross alpha radioactivity, attributed predominantly to Pu and Am, was reduced from 3.14E+04 dps/mL to 1.46 dps/mL in three successive batch contacts with fresh TRUEX solvent. This reduction corresponds to a decontamination factor of DF = 20,000 or 99.995% removal of the gross a activity in the feed. The TRUEX solvent also extracted the matrix components Zr, Fe, and Hg to an appreciable extent (D{sub Zr} > 10, D{sub Fe} {approx} 2, D{sub Hg} {approx}6). Iron co-extracted with the actinides can be successfully scrubbed from the organic with 0.2 M HNO{sub 3}. Mercury can be selectively partitioned from the actinides with either sodium carbonate or nitric acid ({ge} 5 M HNO{sub 3}) solutions.

Physical Description

23 p.

Notes

INIS; OSTI as DE96001188

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  • Other Information: PBD: Mar 1995

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  • Other: DE96001188
  • Report No.: INEL--95/0224
  • Grant Number: AC07-94ID13223
  • DOI: 10.2172/114583 | External Link
  • Office of Scientific & Technical Information Report Number: 114583
  • Archival Resource Key: ark:/67531/metadc626091

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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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Creation Date

  • March 1995

Added to The UNT Digital Library

  • June 16, 2015, 7:43 a.m.

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  • April 18, 2016, 3:39 p.m.

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Herbst, R. S.; Brewer, K. N.; Tranter, T. J. & Todd, T. A. TRUEX partitioning from radioactive ICPP sodium bearing waste, report, March 1995; Batavia, Illinois. (digital.library.unt.edu/ark:/67531/metadc626091/: accessed October 17, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.