ENDF/B-V and ENDF/B-VI results for UO-2 lattice benchmark problems using MCNP Metadata

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Title

  • Main Title ENDF/B-V and ENDF/B-VI results for UO-2 lattice benchmark problems using MCNP

Creator

  • Author: Mosteller, R. D.
    Creator Type: Personal

Contributor

  • Sponsor: United States. Department of Energy.
    Contributor Type: Organization
    Contributor Info: USDOE, Washington, DC (United States)

Publisher

  • Name: Los Alamos National Laboratory
    Place of Publication: New Mexico
    Additional Info: Los Alamos National Lab., Nonproliferation and International Security Div., NM (United States)

Date

  • Creation: 1998-08

Language

  • English

Description

  • Content Description: Calculations for the ANS UO{sub 2} lattice benchmark have been performed with the MCNP Monte Carlo code and its ENDF/B-V and EnDF/B-VI continuous-energy libraries. Similar calculations were performed previously for the experiments upon which these benchmarks are based, using continuous-energy libraries derived from EnDF/B-V and from Release 2 of EnDF/B-VI (ENDF/B-VI.2). This study extends those calculations to the infinite-lattice configurations given in the benchmark specifications and also includes results from Release 3 of EnDF/B-VI (ENDF/B-VI.3) for both the core and infinite-lattice configurations. For this set of benchmarks, the only significant difference between the ENDF/B-VI.2 and EnDF/B-VI.3 libraries is the cross-section behavior of {sup 235}U. EnDF/B-VI.3 contains revised cross sections for {sup 235}U below 900 eV, although those changes principally affect the range below 110 eV. In particular, relative to EnDF/B-VI.2, EnDF/B-VI.3 increases the epithermal capture-to-fission ratio for {sup 235}U and slightly increases its thermal fission cross section.
  • Physical Description: 11 p.

Subject

  • Keyword: Capture-To-Fission Ratio
  • Keyword: Power Distribution
  • Keyword: Multiplication Factors
  • Keyword: Uranium Oxides
  • STI Subject Categories: 22 Nuclear Reactor Technology
  • Keyword: Reactor Lattices
  • Keyword: Nuclear Data Collections
  • Keyword: Benchmarks
  • Keyword: Uranium 235
  • Keyword: Comparative Evaluations
  • Keyword: Research Reactors

Source

  • Conference: International conference on the physics of nuclear science and technology, Long Island, NY (United States), 5-8 Oct 1998

Collection

  • Name: Office of Scientific & Technical Information Technical Reports
    Code: OSTI

Institution

  • Name: UNT Libraries Government Documents Department
    Code: UNTGD

Resource Type

  • Article

Format

  • Text

Identifier

  • Other: DE98007154
  • Report No.: LA-UR--98-23
  • Report No.: CONF-981003--
  • Grant Number: W-7405-ENG-36
  • Office of Scientific & Technical Information Report Number: 674737
  • Archival Resource Key: ark:/67531/metadc710489

Note

  • Display Note: INIS; OSTI as DE98007154
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