Experimental validation of lead cross sections for scale and MCNP

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Description

Moving spent nuclear fuel between facilities often requires the use of lead-shielded casks. Criticality safety that is based upon calculations requires experimental validation of the fuel matrix and lead cross section libraries. A series of critical experiments using a high-enriched uranium-aluminum fuel element with a variety of reflectors, including lead, has been identified. Twenty-one configurations were evaluated in this study. The fuel element was modelled for KENO V.a and MCNP 4a using various cross section sets. The experiments addressed in this report can be used to validate lead-reflected calculations. Factors influencing calculated k{sub eff} which require further study include diameters ... continued below

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8 p.

Creation Information

Henrikson, D.J. December 1, 1995.

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  • EG & G, Inc.
    Publisher Info: EG and G Idaho, Inc., Idaho Falls, ID (United States)
    Place of Publication: Idaho Falls, Idaho

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Description

Moving spent nuclear fuel between facilities often requires the use of lead-shielded casks. Criticality safety that is based upon calculations requires experimental validation of the fuel matrix and lead cross section libraries. A series of critical experiments using a high-enriched uranium-aluminum fuel element with a variety of reflectors, including lead, has been identified. Twenty-one configurations were evaluated in this study. The fuel element was modelled for KENO V.a and MCNP 4a using various cross section sets. The experiments addressed in this report can be used to validate lead-reflected calculations. Factors influencing calculated k{sub eff} which require further study include diameters of styrofoam inserts and homogenization.

Physical Description

8 p.

Notes

INIS; OSTI as DE96002522

Source

  • 5. international conference on nuclear criticality safety, Albuquerque, NM (United States), 17-22 Sep 1995

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  • Other: DE96002522
  • Report No.: INEL--95/00303
  • Report No.: CONF-9509100--131
  • Grant Number: AC07-94ID13223
  • Office of Scientific & Technical Information Report Number: 135033
  • Archival Resource Key: ark:/67531/metadc619761

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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

  • December 1, 1995

Added to The UNT Digital Library

  • June 16, 2015, 7:43 a.m.

Description Last Updated

  • April 26, 2016, 5:07 p.m.

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Henrikson, D.J. Experimental validation of lead cross sections for scale and MCNP, article, December 1, 1995; Idaho Falls, Idaho. (digital.library.unt.edu/ark:/67531/metadc619761/: accessed October 20, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.