Analytical support for characterization of americium-curium solution at SRS

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Americium-Curium (Am-Cm) solution in F-Canyon was produced during the Mk 40 and Mk 41 campaigns in the mid and late 1970`s. The Savannah River Site (SRS) Central Laboratory recently characterized this important solution of nuclear material to enable assessment by Westinghouse Savannah River Company and Department of Energy of disposition options. The tank had last been sampled and analyzed in 1986. A wide range of analyses were performed to determine the tank contents. New radiochemical column separation methods were developed to fully characterize the solution for actinides, metals, anions, and isotopics to support the disposition study in a timely manner. ... continued below

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7 p.

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Maxwell, S.L. III & Nelson, M.R. October 1, 1996.

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Description

Americium-Curium (Am-Cm) solution in F-Canyon was produced during the Mk 40 and Mk 41 campaigns in the mid and late 1970`s. The Savannah River Site (SRS) Central Laboratory recently characterized this important solution of nuclear material to enable assessment by Westinghouse Savannah River Company and Department of Energy of disposition options. The tank had last been sampled and analyzed in 1986. A wide range of analyses were performed to determine the tank contents. New radiochemical column separation methods were developed to fully characterize the solution for actinides, metals, anions, and isotopics to support the disposition study in a timely manner. Current disposition is to perform a vitrification process on the Am/Cm solution at SRS to produce glass canisters for safe shipment and storage of this material. The SRS Am/Cm waste solution will be converted, in effect, to a product for an outside customer. Oak Ridge National Laboratory. To support the Am/Cm vitrification processing, process support analyses are required after completion of denitration, precipitation and redissolution steps. Full elemental chemistry characterization will be required on the final melter feed solution.

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7 p.

Notes

INIS; OSTI as DE97000421

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  • 37. annual meeting of the Institute of Nuclear Materials Management, Naples, FL (United States), 28 Jul - 1 Aug 1996

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  • Other: DE97000421
  • Report No.: WSRC-MS--96-0144
  • Report No.: CONF-960767--73
  • Grant Number: AC09-89SR18035
  • Office of Scientific & Technical Information Report Number: 383596
  • Archival Resource Key: ark:/67531/metadc684989

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Office of Scientific & Technical Information Technical Reports

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  • October 1, 1996

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  • July 25, 2015, 2:20 a.m.

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  • Feb. 9, 2016, 4:39 p.m.

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Maxwell, S.L. III & Nelson, M.R. Analytical support for characterization of americium-curium solution at SRS, article, October 1, 1996; Aiken, South Carolina. (digital.library.unt.edu/ark:/67531/metadc684989/: accessed November 12, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.