Glass as a waste form for the immobilization of plutonium

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Several alternatives for disposal of surplus plutonium are being considered. One method is incorporating Pu into glass and in this paper we discuss the development and corrosion behavior of an alkali-tin-silicate glass and update results in testing Pu doped Defense Waste Processing Facility (DWPF) reference glasses. The alkali-tin-silicate glass was engineered to accommodate a high Pu loading and to be durable under conditions likely to accelerate glass reaction. The glass dissolves about 7 wt% Pu together with the neutron absorber Gd, and under test conditions expected to accelerate the glass reaction with water, is resistant to corrosion. The Pu and ... continued below

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9 p.

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Bates, J.K.; Ellison, A.J.G.; Emery, J.W. & Hoh, J.C. December 31, 1995.

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Description

Several alternatives for disposal of surplus plutonium are being considered. One method is incorporating Pu into glass and in this paper we discuss the development and corrosion behavior of an alkali-tin-silicate glass and update results in testing Pu doped Defense Waste Processing Facility (DWPF) reference glasses. The alkali-tin-silicate glass was engineered to accommodate a high Pu loading and to be durable under conditions likely to accelerate glass reaction. The glass dissolves about 7 wt% Pu together with the neutron absorber Gd, and under test conditions expected to accelerate the glass reaction with water, is resistant to corrosion. The Pu and the Gd are released from the glass at nearly the same rate in static corrosion tests in water, and are not segregated into surface alteration phases when the glass is reacted in water vapor. Similar results for the behavior of Pu and Gd are found for the DWPF reference glasses, although the long-term rate of reaction for the reference glasses is more rapid than for the alkali-tin-silicate glass.

Physical Description

9 p.

Notes

INIS; OSTI as DE96007215

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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: DE96007215
  • Report No.: ANL/CMT/CP--86908
  • Report No.: CONF-951155--61
  • Grant Number: W-31-109-ENG-38
  • Office of Scientific & Technical Information Report Number: 207034
  • Archival Resource Key: ark:/67531/metadc671659

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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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  • December 31, 1995

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  • June 29, 2015, 9:42 p.m.

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  • Dec. 17, 2015, 1:09 p.m.

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Bates, J.K.; Ellison, A.J.G.; Emery, J.W. & Hoh, J.C. Glass as a waste form for the immobilization of plutonium, article, December 31, 1995; Illinois. (digital.library.unt.edu/ark:/67531/metadc671659/: accessed August 16, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.