A simplified radionuclide source term for total-system performance assessment; Yucca Mountain Site Characterization Project

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Description

A parametric model for releases of radionuclides from spent-nuclear-fuel containers in a waste repository is presented. The model is appropriate for use in preliminary total-system performance assessments of the potential repository site at Yucca Mountain, Nevada; for this reason it is simpler than the models used for detailed studies of waste-package performance. Terms are included for releases from the spent fuel pellets, from the pellet/cladding gap and the grain boundaries within the fuel pellets, from the cladding of the fuel rods, and from the radioactive fuel-assembly parts. Multiple barriers are considered, including the waste container, the fuel-rod cladding, the thermal ... continued below

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72 p.

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Wilson, M.L. November 1, 1991.

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This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. More information about this report can be viewed below.

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  • Sandia National Laboratories
    Publisher Info: Sandia National Labs., Albuquerque, NM (United States)
    Place of Publication: Albuquerque, New Mexico

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Description

A parametric model for releases of radionuclides from spent-nuclear-fuel containers in a waste repository is presented. The model is appropriate for use in preliminary total-system performance assessments of the potential repository site at Yucca Mountain, Nevada; for this reason it is simpler than the models used for detailed studies of waste-package performance. Terms are included for releases from the spent fuel pellets, from the pellet/cladding gap and the grain boundaries within the fuel pellets, from the cladding of the fuel rods, and from the radioactive fuel-assembly parts. Multiple barriers are considered, including the waste container, the fuel-rod cladding, the thermal ``dry-out``, and the waste form itself. The basic formulas for release from a single fuel rod or container are extended to formulas for expected releases for the whole repository by using analytic expressions for probability distributions of some important parameters. 39 refs., 4 figs., 4 tabs.

Physical Description

72 p.

Notes

INIS; OSTI as DE92004755

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  • Other Information: PBD: Nov 1991

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  • Other: DE92004755
  • Report No.: SAND--91-0155
  • Grant Number: AC04-76DP00789
  • DOI: 10.2172/138255 | External Link
  • Office of Scientific & Technical Information Report Number: 138255
  • Archival Resource Key: ark:/67531/metadc618451

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  • November 1, 1991

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  • June 16, 2015, 7:43 a.m.

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  • April 14, 2016, 12:41 p.m.

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Wilson, M.L. A simplified radionuclide source term for total-system performance assessment; Yucca Mountain Site Characterization Project, report, November 1, 1991; Albuquerque, New Mexico. (digital.library.unt.edu/ark:/67531/metadc618451/: accessed September 24, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.