RETENTION OF SULFATE IN HIGH LEVEL RADIOACTIVE WASTE GLASS

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High level radioactive wastes are being vitrified at the Savannah River Site for long term disposal. Many of the wastes contain sulfate at concentrations that can be difficult to retain in borosilicate glass. This study involves efforts to optimize the composition of a glass frit for combination with the waste to improve sulfate retention while meeting other process and product performance constraints. The fabrication and characterization of several series of simulated waste glasses are described. The experiments are detailed chronologically, to provide insight into part of the engineering studies used in developing frit compositions for an operating high level waste … continued below

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Fox, K. September 7, 2010.

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High level radioactive wastes are being vitrified at the Savannah River Site for long term disposal. Many of the wastes contain sulfate at concentrations that can be difficult to retain in borosilicate glass. This study involves efforts to optimize the composition of a glass frit for combination with the waste to improve sulfate retention while meeting other process and product performance constraints. The fabrication and characterization of several series of simulated waste glasses are described. The experiments are detailed chronologically, to provide insight into part of the engineering studies used in developing frit compositions for an operating high level waste vitrification facility. The results lead to the recommendation of a specific frit composition and a concentration limit for sulfate in the glass for the next batch of sludge to be processed at Savannah River.

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  • Journal Name: International Journal of Applied Glass Science

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  • Report No.: SRNL-STI-2010-00540
  • Grant Number: DE-AC09-08SR22470
  • Office of Scientific & Technical Information Report Number: 989201
  • Archival Resource Key: ark:/67531/metadc1013642

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  • September 7, 2010

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  • Oct. 14, 2017, 8:36 a.m.

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  • May 11, 2018, 12:48 p.m.

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Fox, K. RETENTION OF SULFATE IN HIGH LEVEL RADIOACTIVE WASTE GLASS, article, September 7, 2010; [Aiken,] South Carolina. (https://digital.library.unt.edu/ark:/67531/metadc1013642/: accessed April 25, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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