Reactivity of high plutonium-containing glasses for the immobilization of surplus fissile materials Metadata

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  • Main Title Reactivity of high plutonium-containing glasses for the immobilization of surplus fissile materials


  • Author: Bates, J.K.
    Creator Type: Personal
  • Author: Hoh, J.C.
    Creator Type: Personal
  • Author: Emery, J.W.
    Creator Type: Personal
  • Author: Buck, E.C.
    Creator Type: Personal
  • Author: Fortner, J.A.
    Creator Type: Personal
  • Author: Wolf, S.F.
    Creator Type: Personal
  • Author: Johnson, T.R.
    Creator Type: Personal


  • Sponsor: United States. Department of Energy.
    Contributor Type: Organization
    Contributor Info: USDOE, Washington, DC (United States)


  • Name: Argonne National Laboratory
    Place of Publication: Idaho Falls, Idaho
    Additional Info: Argonne National Lab., Idaho Falls, ID (United States)


  • Creation: 1995-06-01


  • English


  • Content Description: Experiments have been performed on glasses doped with 2 and 7 wt % plutonium to evaluate factors that may be important in the performance of these high-Pu-loaded glasses for repository storage. The high Pu loadings result from the need to dispose of excess Pu from weapons dismantling. The glasses were reacted in water vapor to simulate aging that may occur under unsaturated storage conditions prior to contact with liquid water. They were also reacted with liquid water under standard static leach test conditions. The results were compared with similar tests of a reference glass (202 glass) containing only 0.01 wt % Pu. In vapor hydration testing to date, at 2 wt % loading, the Pu was incorporated into the glass without phase separation, and reaction in water vapor proceeded at a rate comparable with that of the 202 glass. At wt % loading, a Pu phase separated and was not uniformly incorporated into the glass. The vapor reaction of this glass proceeded at a more rapid rate. This phase separation was manifested in the static leach tests, where colloidal phases of Pu-rich material remained suspended in solution, thereby increasing the absolute Pu release when compared to the 202 glass.
  • Physical Description: 8 p.


  • Keyword: Radioactive Waste Processing
  • STI Subject Categories: 05 Nuclear Fuels
  • Keyword: Nuclear Weapons Dismantlement
  • Keyword: Vitrification
  • Keyword: Fissile Materials
  • Keyword: Plutonium
  • Keyword: Borosilicate Glass


  • Conference: International high-level radioactive waste management conference: progress toward understanding, Las Vegas, NV (United States), 1-5 May 1995


  • Name: Office of Scientific & Technical Information Technical Reports
    Code: OSTI


  • Name: UNT Libraries Government Documents Department
    Code: UNTGD

Resource Type

  • Article


  • Text


  • Other: DE95013472
  • Report No.: ANL/CMT/CP--84882
  • Report No.: CONF-950570--31
  • Grant Number: W-31-109-ENG-38
  • Office of Scientific & Technical Information Report Number: 80883
  • Archival Resource Key: ark:/67531/metadc734006


  • Display Note: INIS; OSTI as DE95013472