Conservative axial burnup distributions for actinide-only burnup credit

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Unlike the fresh fuel approach, which assumes the initial isotopic compositions for criticality analyses, any burnup credit methodology must address the proper treatment of axial burnup distributions. A straightforward way of treating a given axial burnup distribution is to segment the fuel assembly into multiple meshes and to model each burnup mesh with the corresponding isotopic compositions. Although this approach represents a significant increase in modeling efforts compared to the uniform average burnup approach, it can adequately determine the reactivity effect of the axial burnup distribution. A major consideration is what axial burnup distributions are appropriate for use in light ... continued below

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8 p.

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Kang, C. & Lancaster, D. November 1, 1997.

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Description

Unlike the fresh fuel approach, which assumes the initial isotopic compositions for criticality analyses, any burnup credit methodology must address the proper treatment of axial burnup distributions. A straightforward way of treating a given axial burnup distribution is to segment the fuel assembly into multiple meshes and to model each burnup mesh with the corresponding isotopic compositions. Although this approach represents a significant increase in modeling efforts compared to the uniform average burnup approach, it can adequately determine the reactivity effect of the axial burnup distribution. A major consideration is what axial burnup distributions are appropriate for use in light of many possible distributions depending on core operating conditions and histories. This paper summarizes criticality analyses performed to determine conservative axial burnup distributions. The conservative axial burnup distributions presented in this paper are included in the Topical Report on Actinide-Only Burnup Credit for Pressurized Water Reactor Spent Nuclear Fuel Packages, Revision 1 submitted in May 1997 by the US Department of Energy (DOE) to the US Nuclear Regulatory Commission (NRC). When approved by NRC, the conservative axial burnup distributions may be used to model PWR spent nuclear fuel for the purpose of gaining actinide only burnup credit.

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8 p.

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INIS; OSTI as DE98001300

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  • 1998 international high-level radioactive waste management conference, Las Vegas, NV (United States), 11-14 May 1998

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  • Other: DE98001300
  • Report No.: DOE/RW/00134--M97-019
  • Report No.: CONF-980516--
  • Grant Number: AC08-91RW00134
  • Office of Scientific & Technical Information Report Number: 645517
  • Archival Resource Key: ark:/67531/metadc693406

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  • November 1, 1997

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  • Aug. 14, 2015, 8:43 a.m.

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  • May 18, 2016, 5:30 p.m.

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Kang, C. & Lancaster, D. Conservative axial burnup distributions for actinide-only burnup credit, article, November 1, 1997; United States. (digital.library.unt.edu/ark:/67531/metadc693406/: accessed November 17, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.