Preparation and Characterization of {sup 238}Pu-Ceramics for Radiation Damage Experiments Metadata

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  • Main Title Preparation and Characterization of {sup 238}Pu-Ceramics for Radiation Damage Experiments


  • Author: Strachan, Denis M
    Creator Type: Personal
  • Author: Scheele, Randall D
    Creator Type: Personal
  • Author: Buchmiller, William C
    Creator Type: Personal
  • Author: Vienna, John D
    Creator Type: Personal
  • Author: Sell, Richard L
    Creator Type: Personal
  • Author: Elovich, Robert J
    Creator Type: Personal


  • Sponsor: United States. Department of Energy.
    Contributor Type: Organization
    Contributor Info: US Department of Energy (United States)


  • Name: Pacific Northwest National Laboratory (U.S.)
    Place of Publication: Richland, Washington
    Additional Info: Pacific Northwest National Laboratory, Richland, WA (United States)


  • Creation: 2000-06-15


  • English


  • Content Description: The results from this initial characterization of the {sup 238}Pu- and {sup 239}Pu-bearing ceramics showed that the target phase assemblage was achieved in all but one material, {sup 238}Pu-zirconolite baseline. This {sup 238}Pu-zirconolite baseline material appears to have been prepared incorrectly with a 14 mass% excess of Pu (9.6 mass% actual vs. 8.4 mass% target; 4.8 mole% actual vs. 4.1 mole% target). It is not surprising that PuO{sub 2} was found to be one of the dominant phases. The densities of these materials compared well with the theoretical densities given by Stewart, Vance, and Ball [14]. For all but three of the materials, the average density was >94% of theoretical. Of the three, one was {sup 238}Pu-zirconolite baseline (108%) that contained unreacted PuO{sub 2}. In our MCC leach testing, the normalized elemental mass losses from the various ceramic specimens depended on the elemental ceramic constituent, the Pu isotope, and the ceramic. Of the primary constituents, Al and Ca were the most easily released. Plutonium and U were the next most susceptible to release. In general, the Hf had the lowest releases during the tests. The Gd and Ti releases varied, depending on the ceramic and the Pu isotope in the ceramic. The Mo, which was added as a trace constituent to monitor the stability of the crystalline structure, exhibited consistently high-normalized elemental releases. The amount of Pu leached depended the most on the Pu isotope in the ceramic with more Pu released from the {sup 238}Pu specimens than from the {sup 239}Pu specimens, independent of ceramic type. Interestingly, the Mo releases were typically higher for the {sup 239}Pu specimens than for the {sup 238}Pu specimens. The higher Pu release from the {sup 238}Pu specimens is not yet understood; the consistency between the ICP/MS- and GEA-measured Pu releases from the {sup 238}Pu specimens eliminates analytical problems as an explanation. With respect to the effects of ceramic type, the three baseline ceramics often had the highest releases. The highest Pu releases were from the pyrochlore-rich and zirconolite-rich baselines. The highest U releases were from the pyrochlore-rich and zirconolite-rich baselines and zirconolite. Values for the pH of the leachates were deemed unreliable because of the length of time between the end of the test and the measurement. This resulted in pH values that were consistent with CO{sub 2}-saturated water at ambient conditions. However, initial calculations with EQ3/6 suggest that the measured pH values are to be expected, given the solution concentrations and the assumptions that went into the calculations.
  • Physical Description: 46 pages


  • Keyword: Leaching
  • Keyword: Aluminium
  • Keyword: Uranium
  • Keyword: Molybdenum
  • Keyword: Waste Forms
  • Keyword: Density
  • Keyword: Gadolinium
  • STI Subject Categories: 36 Materials Science
  • Keyword: Titanium
  • Keyword: Leachates
  • Keyword: Materials Testing
  • Keyword: Plutonium Oxides
  • Keyword: Zirconolite
  • Keyword: Calcium
  • Keyword: Radionuclide Migration
  • STI Subject Categories: 12 Management Of Radioactive Wastes, And Non-Radioactive Wastes From Nuclear Facilities
  • Keyword: Plutonium 238
  • Keyword: Plutonium 239
  • Keyword: Ph Value
  • Keyword: Ceramics
  • Keyword: Radioactive Waste Disposal


  • Other Information: PBD: 15 Jun 2000


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


  • Name: UNT Libraries Government Documents Department
    Code: UNTGD

Resource Type

  • Report


  • Text


  • Report No.: NONE
  • Report No.: NN6001020
  • DOI: 10.2172/781061
  • Office of Scientific & Technical Information Report Number: 781061
  • Archival Resource Key: ark:/67531/metadc723022