A deformation and thermodynamic model for hydride precipitation kinetics in spent fuel cladding

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Hydrogen is contained in the Zircaloy cladding of spent fuel rods from nuclear reactors. All the spent fuel rods placed in a nuclear waste repository will have a temperature history that decreases toward ambient; and as a result, most all of the hydrogen in the Zircaloy will eventually precipitate as zirconium hydride platelets. A model for the density of hydride platelets is a necessary sub-part for predicting Zircaloy cladding failure rate in a nuclear waste repository. A model is developed to describe statistically the hydride platelet density, and the density function includes the orientation as a physical attribute. The model ... continued below

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28 p.

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Stout, R.B. October 1, 1989.

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Hydrogen is contained in the Zircaloy cladding of spent fuel rods from nuclear reactors. All the spent fuel rods placed in a nuclear waste repository will have a temperature history that decreases toward ambient; and as a result, most all of the hydrogen in the Zircaloy will eventually precipitate as zirconium hydride platelets. A model for the density of hydride platelets is a necessary sub-part for predicting Zircaloy cladding failure rate in a nuclear waste repository. A model is developed to describe statistically the hydride platelet density, and the density function includes the orientation as a physical attribute. The model applies concepts from statistical mechanics to derive probable deformation and thermodynamic functionals for cladding material response that depend explicitly on the hydride platelet density function. From this model, hydride precipitation kinetics depend on a thermodynamic potential for hydride density change and on the inner product of a stress tensor and a tensor measure for the incremental volume change due to hydride platelets. The development of a failure response model for Zircaloy cladding exposed to the expected conditions in a nuclear waste repository is supported by the US DOE Yucca Mountain Project. 19 refs., 3 figs.

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28 p.

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INIS; OSTI as DE90008541

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  • Materials Research Society fall meeting, Boston, MA (United States), 27 Nov - 2 Dec 1989

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  • Other: DE90008541
  • Report No.: UCRL--100860
  • Report No.: CONF-891119--109
  • Grant Number: W-7405-ENG-48
  • Office of Scientific & Technical Information Report Number: 137685
  • Archival Resource Key: ark:/67531/metadc619926

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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.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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  • October 1, 1989

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  • June 16, 2015, 7:43 a.m.

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  • Feb. 18, 2016, 12:19 p.m.

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Stout, R.B. A deformation and thermodynamic model for hydride precipitation kinetics in spent fuel cladding, article, October 1, 1989; California. (digital.library.unt.edu/ark:/67531/metadc619926/: accessed November 19, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.