Radionuclide distribution in LWR [light-water reactor] spent fuel

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The Materials Characterization Center (MCC) at Pacific Northwest Laboratory (PNL) provides well-characterized spent fuel from light-water reactors (LWRs) for use in laboratory tests relevant to nuclear waste disposal in the proposed Yucca Mountain repository. Interpretation of results from tests on spent fuel oxidation, dissolution, and cladding degradation requires information on the inventory and distribution of radionuclides in the initial test materials. The MCC is obtaining this information from examinations of Approved Testing Materials (ATMs), which include spent fuel with burnups from 17 to 50 MWd/kgM and fission gas releases (FGR) from 0.2 to 18%. The concentration and distribution of activation ... continued below

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5 p.

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Guenther, R.J.; Blahnik, D.E.; Thomas, L.E.; Baldwin, D.L. & Mendel, J.E. September 1, 1990.

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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

The Materials Characterization Center (MCC) at Pacific Northwest Laboratory (PNL) provides well-characterized spent fuel from light-water reactors (LWRs) for use in laboratory tests relevant to nuclear waste disposal in the proposed Yucca Mountain repository. Interpretation of results from tests on spent fuel oxidation, dissolution, and cladding degradation requires information on the inventory and distribution of radionuclides in the initial test materials. The MCC is obtaining this information from examinations of Approved Testing Materials (ATMs), which include spent fuel with burnups from 17 to 50 MWd/kgM and fission gas releases (FGR) from 0.2 to 18%. The concentration and distribution of activation products and the release of volatile fission products to the pellet-cladding gap and rod plenum are of particular interest because these characteristics are not well understood. This paper summarizes results that help define the {sup 14}C inventory and distribution in cladding, the ``gap and grain boundary`` inventory of radionuclides in fuels with different FGRs, and the structure and radionuclide inventory of the fuel rim region within a few hundred micrometers from the fuel edge. 6 refs., 5 figs., 1 tab.

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5 p.

Notes

INIS; OSTI as DE91002806

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  • Spectrum `90: American Nuclear Society (ANS) international meeting on radioactive waste technologies, decontamination, and hazardous wastes, Knoxville, TN (United States), 30 Sep - 4 Oct 1990

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  • Other: DE91002806
  • Report No.: PNL-SA--18168
  • Report No.: CONF-900977--5
  • Grant Number: AC06-76RL01830
  • Office of Scientific & Technical Information Report Number: 137931
  • Archival Resource Key: ark:/67531/metadc619408

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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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  • September 1, 1990

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  • June 16, 2015, 7:43 a.m.

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  • April 7, 2016, 6:40 p.m.

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Guenther, R.J.; Blahnik, D.E.; Thomas, L.E.; Baldwin, D.L. & Mendel, J.E. Radionuclide distribution in LWR [light-water reactor] spent fuel, article, September 1, 1990; Richland, Washington. (digital.library.unt.edu/ark:/67531/metadc619408/: accessed May 24, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.