Macroscopic cross sections for the management of weapons-grade Pu fuels in BWRs

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One possible method to reduce the enrichment of the surplus of weapons-grade plutonium is to irradiate mixed oxide fuels (MOX) in commercial nuclear reactors like the boiling water reactors built by General Electric. Contributions to evaluate this possibility are currently made by the Oak Ridge National Laboratory (ORNL) and its contractors. Because important decisions are to be made based on calculations, the calculational procedures, in particular the two-dimensional Scandpower proprietary code HELIOS, were benchmarked against available experience with near weapons-grade Pu fuel and against other codes. In this work the authors report their calculations of diffusion theory macroscopic cross section ... continued below

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5 p.

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Difilippo, F.C. November 1, 1998.

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This article 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 article can be viewed below.

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  • Oak Ridge National Laboratory
    Publisher Info: Oak Ridge National Lab., Computational Physics and Engineering Div., TN (United States)
    Place of Publication: Tennessee

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Description

One possible method to reduce the enrichment of the surplus of weapons-grade plutonium is to irradiate mixed oxide fuels (MOX) in commercial nuclear reactors like the boiling water reactors built by General Electric. Contributions to evaluate this possibility are currently made by the Oak Ridge National Laboratory (ORNL) and its contractors. Because important decisions are to be made based on calculations, the calculational procedures, in particular the two-dimensional Scandpower proprietary code HELIOS, were benchmarked against available experience with near weapons-grade Pu fuel and against other codes. In this work the authors report their calculations of diffusion theory macroscopic cross section as a function of burnup, for different combinations of operational parameters. These results are to be input later to the code FORMOSA-B, developed at North Carolina State University (NCSU), to study fuel management strategies in the long range operation of BWR`s with MOX fuels. Seventeen cases for various conditions of the fuel assemblies were specified by NCSU. These correspond to different combinations of void fractions, fuel temperatures, control rods and history.

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5 p.

Notes

INIS; OSTI as DE99000368

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  • American Nuclear Society winter meeting, Washington, DC (United States), 15-19 Nov 1998

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  • Other: DE99000368
  • Report No.: ORNL/CP--98903
  • Report No.: CONF-981106--
  • Grant Number: AC05-96OR22464
  • Office of Scientific & Technical Information Report Number: 677201
  • Archival Resource Key: ark:/67531/metadc702473

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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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  • November 1, 1998

Added to The UNT Digital Library

  • Sept. 12, 2015, 6:31 a.m.

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  • Nov. 3, 2016, 6:48 p.m.

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Difilippo, F.C. Macroscopic cross sections for the management of weapons-grade Pu fuels in BWRs, article, November 1, 1998; Tennessee. (digital.library.unt.edu/ark:/67531/metadc702473/: accessed October 18, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.