Spent fuel waste form characteristics: Grain and fragment size statistical dependence for dissolution response

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The Yucca Mountain Project of the US Department of Energy is investigating the suitability of the unsaturated zone at Yucca Mountain, NV, for a high-level nuclear waste repository. All of the nuclear waste will be enclosed in a container package. Most of the nuclear waste will be in the form of fractured UO{sub 2} spent fuel pellets in Zircaloy-clad rods from electric power reactors. If failure of both the container and its enclosed clad rods occurs, then the fragments of the fractured UO{sub 2} spent fuel will be exposed to their surroundings. Even though the surroundings are an unsaturated zone, ... continued below

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24 p.

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Stout, R.B.; Leider, H.; Weed, H.; Nguyen, S.; McKenzie, W.; Prussin, S. et al. April 1, 1991.

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Description

The Yucca Mountain Project of the US Department of Energy is investigating the suitability of the unsaturated zone at Yucca Mountain, NV, for a high-level nuclear waste repository. All of the nuclear waste will be enclosed in a container package. Most of the nuclear waste will be in the form of fractured UO{sub 2} spent fuel pellets in Zircaloy-clad rods from electric power reactors. If failure of both the container and its enclosed clad rods occurs, then the fragments of the fractured UO{sub 2} spent fuel will be exposed to their surroundings. Even though the surroundings are an unsaturated zone, a possibility of water transport exists, and consequently, UO{sub 2} spent fuel dissolution may occur. A repository requirement imposes a limit on the nuclide release per year during a 10,000 year period; thus the short term dissolution response from fragmented fuel pellet surfaces in any given year must be understood. This requirement necessitates that both experimental and analytical activities be directed toward predicting the relatively short term dissolution response of UO{sub 2} spent fuel. The short term dissolution response involves gap nuclides, grain boundary nuclides, and grain volume nuclides. Analytical expressions are developed that describe the combined geometrical influences of grain boundary nuclides and grain volume nuclides on the dissolution rate of spent fuel. 7 refs., 1 fig.

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24 p.

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INIS; OSTI as DE91012027

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  • 2. annual American Nuclear Society (ANS) international high level radioactive waste management conference, Las Vegas, NV (United States), 28 Apr - 3 May 1991

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  • Other: DE91012027
  • Report No.: UCRL-JC--104931
  • Report No.: CONF-910435--72
  • Grant Number: W-7405-ENG-48
  • Office of Scientific & Technical Information Report Number: 138107
  • Archival Resource Key: ark:/67531/metadc619820

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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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  • April 1, 1991

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  • June 16, 2015, 7:43 a.m.

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  • Feb. 17, 2016, 4:31 p.m.

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Stout, R.B.; Leider, H.; Weed, H.; Nguyen, S.; McKenzie, W.; Prussin, S. et al. Spent fuel waste form characteristics: Grain and fragment size statistical dependence for dissolution response, article, April 1, 1991; California. (digital.library.unt.edu/ark:/67531/metadc619820/: accessed November 20, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.