Reaction progress pathways for glass and spent fuel under unsaturated conditions

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The source term for the release of radionuclides from a nuclear waste repository is the waste form. In order to assess the performance of the repository and the engineered barrier system (EBS) compared to regulations established by the Nuclear Regulatory Commission and the Environmental Protection Agency it is necessary (1) to use available data to place bounding limits on release rates from the EBS, and (2) to develop a mechanistic predictive model of the radionuclide release and validate the model against tests done under a variety of different potential reaction conditions. The problem with (1) is that there is little ... continued below

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4 p.

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Bates, J.; Finn, P.; Bourcier, W. & Stout, R. October 1, 1994.

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Description

The source term for the release of radionuclides from a nuclear waste repository is the waste form. In order to assess the performance of the repository and the engineered barrier system (EBS) compared to regulations established by the Nuclear Regulatory Commission and the Environmental Protection Agency it is necessary (1) to use available data to place bounding limits on release rates from the EBS, and (2) to develop a mechanistic predictive model of the radionuclide release and validate the model against tests done under a variety of different potential reaction conditions. The problem with (1) is that there is little experience to use when evaluating waste form reaction under unsaturated conditions such that errors in applying expert judgment to the problem may be significant. The second approach, to test and model the waste form reaction, is a more defensible means of providing input to the prediction of radionuclide release. In this approach, information related to the source term has a technical basis and provides a starting point to make reasonable assumptions for long-term behavior. Key aspects of this approach are an understanding of the reaction progress mechanism and the ability to model the tests using a geochemical code such as EQ3/6. Current knowledge of glass, UO{sub 2}, and spent fuel reactions under different conditions are described below.

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4 p.

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INIS; OSTI as DE95009472

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

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  • Other: DE95009472
  • Report No.: UCRL-JC--119115
  • Report No.: ANL/CMT/CP--85907;CONF-950570--17
  • Grant Number: W-7405-ENG-48;W-31-109-ENG-38
  • Office of Scientific & Technical Information Report Number: 42466
  • Archival Resource Key: ark:/67531/metadc679457

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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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  • October 1, 1994

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  • July 25, 2015, 2:20 a.m.

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  • Feb. 17, 2016, 3:53 p.m.

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Bates, J.; Finn, P.; Bourcier, W. & Stout, R. Reaction progress pathways for glass and spent fuel under unsaturated conditions, article, October 1, 1994; California. (digital.library.unt.edu/ark:/67531/metadc679457/: accessed December 11, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.