Characterization of and waste acceptance radionuclide to be reported for the 2nd macro-batch of high-level waste sludge being vitrified in the DWPF melter

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The Defense Waste Processing Facility (DWPF), at the Savannah River Site (SRS), is currently processing the second million gallon batch (Macro-Batch 2) of radioactive sludge slurry into a durable borosilicate glass for permanent geological disposal. To meet the reporting requirements as specified in the Department of Energy's Waste Acceptance Product Specifications (WAPS), for the final glass product, the nonradioactive and radioactive compositions must be provided for a Macro-Batch of material. In order to meet this requirement, sludge slurry samples from Macro-Batch 2 were analyzed in the Shielded Cells Facility of the Savannah River Technology Center (SRTC). This information is used ... continued below

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Fellinger, T. L. January 26, 2000.

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The Defense Waste Processing Facility (DWPF), at the Savannah River Site (SRS), is currently processing the second million gallon batch (Macro-Batch 2) of radioactive sludge slurry into a durable borosilicate glass for permanent geological disposal. To meet the reporting requirements as specified in the Department of Energy's Waste Acceptance Product Specifications (WAPS), for the final glass product, the nonradioactive and radioactive compositions must be provided for a Macro-Batch of material. In order to meet this requirement, sludge slurry samples from Macro-Batch 2 were analyzed in the Shielded Cells Facility of the Savannah River Technology Center (SRTC). This information is used to complete the necessary Production Records at DWPF so that the final glass product, resulting from Macro Batch 2, may be disposed of at a Federal Repository. This paper describes the results obtained from the analyses of the sludge slurry samples taken from Macro-Batch 2 to meet the reporting requirements of the WAPS. Twenty eight elements were identified for the nonradioactive composition and thirty one for the radioactive composition. The reportable radioisotopes range from C-14 to Cm-246.

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  • 1999 Materials Research Society Fall Meeting, Boston, MA (US), 11/29/1999--12/02/1999

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  • Report No.: WSRC-MS--99-00852
  • Grant Number: AC09-96SR18500
  • Office of Scientific & Technical Information Report Number: 750907
  • Archival Resource Key: ark:/67531/metadc704548

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  • January 26, 2000

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  • Sept. 12, 2015, 6:31 a.m.

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  • May 5, 2016, 3:43 p.m.

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Fellinger, T. L. Characterization of and waste acceptance radionuclide to be reported for the 2nd macro-batch of high-level waste sludge being vitrified in the DWPF melter, article, January 26, 2000; South Carolina. (digital.library.unt.edu/ark:/67531/metadc704548/: accessed December 14, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.