Determination of BWR Spent Nuclear Fuel Assembly Effective Thermal Conductivity

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Description

The purpose of this calculation is to provide an effective thermal conductivity for use in predicting peak cladding temperatures in boiling water reactor (BWR) fuel assemblies with 7x7,8x8, and 9x9 rod arrays. The first objective of this calculation is to describe the development and application of a finite element representation that predicts peak spent nuclear fuel temperatures for BWR assemblies. The second objective is to use the discrete representation to develop a basis for determining an effective thermal conductivity (described later) for a BWR assembly with srneared/homogeneous properties and to investigate the thermal behavior of a spent fuel assembly. The ... continued below

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193 pages

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Hinds, Matthew D. October 17, 2001.

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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. It has been viewed 16 times . More information about this report can be viewed below.

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Description

The purpose of this calculation is to provide an effective thermal conductivity for use in predicting peak cladding temperatures in boiling water reactor (BWR) fuel assemblies with 7x7,8x8, and 9x9 rod arrays. The first objective of this calculation is to describe the development and application of a finite element representation that predicts peak spent nuclear fuel temperatures for BWR assemblies. The second objective is to use the discrete representation to develop a basis for determining an effective thermal conductivity (described later) for a BWR assembly with srneared/homogeneous properties and to investigate the thermal behavior of a spent fuel assembly. The scope of this calculation is limited to a steady-state two-dimensional representation of the waste package interior region. This calculation is subject to procedure AP-3.124, Calculations (Ref. 27) and guided by the applicable technical work plan (Ref. 14). While these evaluations were originally developed for the thermal analysis of conceptual waste package designs emplaced in the potential repository at Yucca Mountain, the methodology applies to storage and transportation thermal analyses as well. Note that the waste package sketch in Attachment V depicts a preliminary design, and should not be interpreted otherwise.

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193 pages

Notes

INIS; OSTI as DE00790801

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  • Other Information: PBD: 17 Oct 2001

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  • Report No.: CAL-WIS-TH-000011, Rev. 00
  • Grant Number: NONE
  • DOI: 10.2172/790801 | External Link
  • Office of Scientific & Technical Information Report Number: 790801
  • Archival Resource Key: ark:/67531/metadc719789

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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.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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Creation Date

  • October 17, 2001

Added to The UNT Digital Library

  • Sept. 29, 2015, 5:31 a.m.

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  • Feb. 10, 2016, 6:51 p.m.

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Hinds, Matthew D. Determination of BWR Spent Nuclear Fuel Assembly Effective Thermal Conductivity, report, October 17, 2001; Las Vegas, Nevada. (digital.library.unt.edu/ark:/67531/metadc719789/: accessed October 22, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.