Evaluation of glass as a matrix for solidification of Savannah River Plant waste

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Laboratory tests using actual sludges collected from Savannah River Plant (SRP) waste tanks were performed to evaluate glass as a waste solidification matrix. Sludge was collected from three SRP waste tanks, washed to remove soluble salts, and then ground to a fine powder. From 25 to 40 wt percent of these sludges was vitrified into a borosilicate glass by melting at 1150$sup 0$C. Substitution of 4 wt percent Li$sub 2$O for 4 wt percent Na$sub 2$O in the glass mix allowed higher loading of a high-aluminum sludge. No problems with phase separation were encountered, and all sludge components, except mercury ... continued below

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21 p.

Creation Information

Kelley, J.A. October 1, 1975.

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  • Savannah River Laboratory
    Publisher Info: Du Pont de Nemours (E.I.) and Co., Aiken, S.C. (USA). Savannah River Lab.
    Place of Publication: Aiken, South Carolina

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Description

Laboratory tests using actual sludges collected from Savannah River Plant (SRP) waste tanks were performed to evaluate glass as a waste solidification matrix. Sludge was collected from three SRP waste tanks, washed to remove soluble salts, and then ground to a fine powder. From 25 to 40 wt percent of these sludges was vitrified into a borosilicate glass by melting at 1150$sup 0$C. Substitution of 4 wt percent Li$sub 2$O for 4 wt percent Na$sub 2$O in the glass mix allowed higher loading of a high-aluminum sludge. No problems with phase separation were encountered, and all sludge components, except mercury which volatilized, appeared to dissolve completely in the glass melt. Volatilization of radionuclides during melting was 0.3 percent for $sup 137$Cs, 2.9 percent for $sup 106$Ru, and less than or equal to 0.01 percent for other nuclides. Initial leachabilities of glass products were low: 10$sup -6$ to 10$sup -5$ g/(cm$sup 2$-day) for $sup 137$ , $sup 90$Sr, and alpha activity. Leachabilities decreased to 10$sup -8$ to 10$sup -7$ g/(cm$sup 2$- day) in approximately 2 weeks. Heating the glasses at 600$sup 0$C for 1 month caused devitrification which increased leachability, but durable waste forms still remained. This work showed that vitrification of SRP high-level waste sludges in borosilicate glass is feasible. Further investigation of melting concepts, scale- up, cost, long-term stability, and other factors are planned as a part of the development program for long-term waste management. (auth)

Physical Description

21 p.

Notes

Dep. NTIS; 00.

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  • Other Information: Orig. Receipt Date: 30-JUN-76

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  • Report No.: DP--1397
  • Grant Number: None
  • DOI: 10.2172/4184149 | External Link
  • Office of Scientific & Technical Information Report Number: 4184149
  • Archival Resource Key: ark:/67531/metadc868088

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Office of Scientific & Technical Information Technical Reports

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

  • October 1, 1975

Added to The UNT Digital Library

  • Sept. 16, 2016, 12:32 a.m.

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  • Oct. 12, 2017, 4:38 p.m.

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Kelley, J.A. Evaluation of glass as a matrix for solidification of Savannah River Plant waste, report, October 1, 1975; Aiken, South Carolina. (digital.library.unt.edu/ark:/67531/metadc868088/: accessed April 24, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.