Chemical durability of simulated nuclear glasses containing water

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Description

The chemical durability of simulated nuclear waste glasses having different water contents was studied. Results from the product consistency test (PCT) showed that glass dissolution increased with water content in the glass. This trend was not observed during MCC-1 testing. This difference was attributed to the differences in reactions between glass and water. In the PCT, the glass network dissolution controlled the elemental releases, and water in the glass accelerated the reaction rate. On the other hand, alkali ion exchange with hydronium played an important role in the MCC-1. For the latter, the amount of water introduced into a leached ... continued below

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9 p.

Creation Information

Li, H. & Tomozawa, M. April 1, 1995.

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This article is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. More information about this article can be viewed below.

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Authors

  • Li, H. Pacific Northwest Lab., Richland, WA (United States)
  • Tomozawa, M. Rensselaer Polytechnic Inst., Troy, New York (United States)

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  • Pacific Northwest Laboratory
    Publisher Info: Pacific Northwest Lab., Richland, WA (United States)
    Place of Publication: Richland, Washington

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Description

The chemical durability of simulated nuclear waste glasses having different water contents was studied. Results from the product consistency test (PCT) showed that glass dissolution increased with water content in the glass. This trend was not observed during MCC-1 testing. This difference was attributed to the differences in reactions between glass and water. In the PCT, the glass network dissolution controlled the elemental releases, and water in the glass accelerated the reaction rate. On the other hand, alkali ion exchange with hydronium played an important role in the MCC-1. For the latter, the amount of water introduced into a leached layer from ion-exchange was found to be much greater than that of initially incorporated water in the glass. Hence, the initial water content has no effect on glass dissolution as measured by the MCC-1 test.

Physical Description

9 p.

Notes

INIS; OSTI as DE95014178

Source

  • 97. annual meeting of the American Ceramic Society, Cincinnati, OH (United States), 30 Apr - 1 May 1995

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  • Other: DE95014178
  • Report No.: PNL-SA--26219
  • Report No.: CONF-950401--21
  • Grant Number: AC06-76RL01830
  • Office of Scientific & Technical Information Report Number: 101277
  • Archival Resource Key: ark:/67531/metadc619959

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Creation Date

  • April 1, 1995

Added to The UNT Digital Library

  • June 16, 2015, 7:43 a.m.

Description Last Updated

  • April 7, 2016, 2:30 p.m.

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Li, H. & Tomozawa, M. Chemical durability of simulated nuclear glasses containing water, article, April 1, 1995; Richland, Washington. (digital.library.unt.edu/ark:/67531/metadc619959/: accessed August 17, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.