Durabilities and Microstructures of Radioactive Glasses to Immobilize Excess Actinides and Reprocessing Wastes at SRS

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This paper presents results of an investigation of the microstructures and durabilities of glasses for immobilization of excess Pu, Am, and Cm, and of the reprocessing wastes at Savannah River Site (SRS). The reprocessing wastes will be vitrified in the Defense Waste Processing Facility (DWPF) at SRS. Another facility at SRS will be used for the Pu, Am, and Cm glasses. In this paper results are presented for a DWPF radioactive glass containing the actual fission product-actinide waste from one the million gallon storage tanks at SRS. This waste is the first radioactive sludge that will be processed in DWPF. ... continued below

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18 p.

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Bibler, N.E. December 4, 1995.

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This paper presents results of an investigation of the microstructures and durabilities of glasses for immobilization of excess Pu, Am, and Cm, and of the reprocessing wastes at Savannah River Site (SRS). The reprocessing wastes will be vitrified in the Defense Waste Processing Facility (DWPF) at SRS. Another facility at SRS will be used for the Pu, Am, and Cm glasses. In this paper results are presented for a DWPF radioactive glass containing the actual fission product-actinide waste from one the million gallon storage tanks at SRS. This waste is the first radioactive sludge that will be processed in DWPF. The actinide glasses investigated had compositions based on a commercial borosilicate glass composition. All the glasses were so radioactive that they had to be prepared remotely in shielded cells and the analyses had to be performed in gloveboxes or radiobenches. Durabilities were measured using the ASTM C-1285 standard leach test. Results for four glasses are presented. The glasses are a DWPF type glass containing Tank 51 radioactive waste, two glasses containing 15 and 13 wt.percent Pu, respectively, and a glass containing Am and Cm. The radioactive DWPF glass contained 28 wtpercent waste from SRS Tank 51 and was homogeneous. The 15 wt percent Pu contained dissolved PuO2 and as well PuO2 crystals that were not dissolved but were trapped in the glass. The 13 wt percent Pu glass was homogenous. The Am/Cm glass contained <1 wt percent actinides and was homogenous. The PCT test indicated that B, Li, and Na were leaching congruently from the glass. Release rates for Tc-99 and Np-237 were also congruent while Cs-133, Th-232, U-238, and Pu-239 were slower. The two Pu glasses were 25 to 50 times more durable than the DWPF glass. B and Ba were leached congruently while Sm and Pu were lower. Release rates for B and Ba from the Am-Cm glass were equal and 27X lower than the DWPF glass.

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18 p.

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INIS; OSTI as DE96060033

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  • Fall meeting of the Materials Research Society (MRS), Boston, MA (United States), 27 Nov - 1 Dec 1995

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  • Other: DE96060033
  • Report No.: WSRC-MS--95-0503
  • Report No.: CONF-951155--69
  • Grant Number: AC09-89SR18035
  • Office of Scientific & Technical Information Report Number: 206372
  • Archival Resource Key: ark:/67531/metadc666574

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  • December 4, 1995

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  • June 29, 2015, 9:42 p.m.

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  • Feb. 9, 2016, 4:57 p.m.

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Bibler, N.E. Durabilities and Microstructures of Radioactive Glasses to Immobilize Excess Actinides and Reprocessing Wastes at SRS, article, December 4, 1995; Aiken, South Carolina. (digital.library.unt.edu/ark:/67531/metadc666574/: accessed October 19, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.