Investigation of Burnup Credit Issues in BWR Fuel

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Calculations for long-term-disposal criticality safety of spent nuclear fuel requires the application of burnup credit because of the large mass of fissile material that will be present in the repository. Burnup credit calculations are based on depletion calculations that provide a conservative estimate of spent fuel contents, followed by criticality calculations to assess the value of keff for a spent fuel cask or a fuel configuration under a variety of probabilistically derived events. In order to ensure that the depletion calculation is conservative, it is necessary to both qualify and quantify assumptions that can be made in depletion models used ... continued below

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10 pages

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Broadhead, B.L. & DeHart, M.D. September 20, 1999.

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Description

Calculations for long-term-disposal criticality safety of spent nuclear fuel requires the application of burnup credit because of the large mass of fissile material that will be present in the repository. Burnup credit calculations are based on depletion calculations that provide a conservative estimate of spent fuel contents, followed by criticality calculations to assess the value of keff for a spent fuel cask or a fuel configuration under a variety of probabilistically derived events. In order to ensure that the depletion calculation is conservative, it is necessary to both qualify and quantify assumptions that can be made in depletion models used to characterize spent fuel. Most effort in the United States this decade has focused on burnup issues related to pressurized-water reactors. However, requirements for the permanent disposal of fuel from boiling-water reactors has necessitated development of methods for prediction of spent fuel contents for such fuels. Concomitant with such analyses, validation is also necessary. This paper provides a summary of initial efforts at the Oak Ridge National Laboratory to better understand and validate spent fuel analyses for boiling-water-reactor fuel.

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10 pages

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  • ICNC'99, 6th International Conference on Nuclear Criticality Safety, Palais des congres, Versailles, France, September 20-24, 1999

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  • Other: DE00007629
  • Report No.: ORNL/CP-103312
  • Grant Number: AC05-96OR22464
  • Office of Scientific & Technical Information Report Number: 7629
  • Archival Resource Key: ark:/67531/metadc722842

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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 20, 1999

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  • Sept. 29, 2015, 5:31 a.m.

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  • June 20, 2016, 6:05 p.m.

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Broadhead, B.L. & DeHart, M.D. Investigation of Burnup Credit Issues in BWR Fuel, article, September 20, 1999; Oak Ridge, Tennessee. (digital.library.unt.edu/ark:/67531/metadc722842/: accessed November 18, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.