Interlaboratory comparison of UO{sub 2} dissolution rates

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Direct disposal of spent nuclear fuel in deep underground geologic repositories (vaults) is being pursued by several countries. Isolation relies on multiple barriers consisting of the site geology, engineered barriers including containers to surround the fuel, and the spent fuel itself. These barriers are intended to inhibit dissolution and transport of radionuclides by groundwater, which is virtually the only mechanism available to release radionuclides from the repository. Performance assessment studies are needed to demonstrate the adequacy of the various repository designs. Essential to this performance assessment is an understanding of the dissolution behavior of the spent fuel. Since the dissolution ... continued below

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6 p.

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Gray, W.J.; Steward, S.A.; Trait, J.C. & Shoesmith, D.W. May 1, 1994.

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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

Direct disposal of spent nuclear fuel in deep underground geologic repositories (vaults) is being pursued by several countries. Isolation relies on multiple barriers consisting of the site geology, engineered barriers including containers to surround the fuel, and the spent fuel itself. These barriers are intended to inhibit dissolution and transport of radionuclides by groundwater, which is virtually the only mechanism available to release radionuclides from the repository. Performance assessment studies are needed to demonstrate the adequacy of the various repository designs. Essential to this performance assessment is an understanding of the dissolution behavior of the spent fuel. Since the dissolution behavior of spent fuel in an actual repository cannot be adequately approximated in a laboratory, laboratory tests and data must be used to develop a mechanistic model that can predict long-term behavior in a repository. Three different laboratories have performed flowthrough dissolution tests at room temperature on portions of the same batch of unirradiated UO{sub 2} powder, and good agreement was achieved between the different test results. Dissolution rates obtained from electrochemical studies conducted with UO{sub 2} electrodes at Whiteshell Laboratories are compared with the flowthrough test results.

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6 p.

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INIS; OSTI as DE94014413

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  • International high-level radioactive waste management conference, Las Vegas, NV (United States), 22-26 May 1994

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  • Other: DE94014413
  • Report No.: PNL-SA--23748
  • Report No.: UCRL-JC--115356;CONF-940553--71
  • Grant Number: AC06-76RL01830;W-7405-ENG-48
  • Office of Scientific & Technical Information Report Number: 145516
  • Archival Resource Key: ark:/67531/metadc619695

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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.

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  • May 1, 1994

Added to The UNT Digital Library

  • June 16, 2015, 7:43 a.m.

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  • April 7, 2016, 4:43 p.m.

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Gray, W.J.; Steward, S.A.; Trait, J.C. & Shoesmith, D.W. Interlaboratory comparison of UO{sub 2} dissolution rates, article, May 1, 1994; Richland, Washington. (digital.library.unt.edu/ark:/67531/metadc619695/: accessed May 24, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.