International studies on burnup credit criticality safety by an OECD/NEA working group Metadata

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Title

  • Main Title International studies on burnup credit criticality safety by an OECD/NEA working group

Creator

  • Author: Brady, M.C.
    Creator Type: Personal
    Creator Info: Duke Engineering and Services, Inc., Richland, WA (United States)
  • Author: Okuno, H.
    Creator Type: Personal
    Creator Info: Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)
  • Author: DeHart, M.D.
    Creator Type: Personal
    Creator Info: Oak Ridge National Lab., TN (United States)
  • Author: Nouri, A.
    Creator Type: Personal
    Creator Info: Inst. de Protection et de Surete Nucleaire, Fontenay Aux Roses (France)
  • Author: Sartori, E.
    Creator Type: Personal
    Creator Info: Organization for Economic Cooperation and Development/Nuclear Energy Agency, Paris (France)

Contributor

  • Sponsor: United States. Department of Energy. Office of Environmental Restoration and Waste Management.
    Contributor Type: Organization
    Contributor Info: USDOE Office of Environmental Restoration and Waste Management, Washington, DC (United States)

Publisher

  • Name: Oak Ridge National Laboratory
    Place of Publication: Tennessee
    Additional Info: Oak Ridge National Lab., TN (United States)

Date

  • Creation: 1998-11-01

Language

  • English

Description

  • Content Description: The results and conclusions from a six-year study by an international benchmarking group in the comparison of computational methods for evaluating burnup credit in criticality safety analyses is presented. Approximately 20 participants from 12 countries have provided results for most problems. Four detailed benchmark problems for pressurized-water-reactor fuel have been completed. Results from work being finalized, addressing burnup credit for boiling-water-reactor fuel, are discussed, as well as planned activities for additional benchmarks, including mixed-oxide fuels, and other activities.
  • Physical Description: 8 p.

Subject

  • STI Subject Categories: 42 Engineering Not Included In Other Categories
  • Keyword: Bwr Type Reactors
  • Keyword: Criticality
  • Keyword: Spent Fuel Storage
  • STI Subject Categories: 05 Nuclear Fuels
  • Keyword: Pwr Type Reactors
  • Keyword: Spent Fuels
  • Keyword: Benchmarks
  • Keyword: Safety Analysis
  • Keyword: Transport

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: DE99000395
  • Report No.: ORNL/CP--99309
  • Report No.: CONF-981003--
  • Grant Number: AC05-96OR22464
  • Office of Scientific & Technical Information Report Number: 291071
  • Archival Resource Key: ark:/67531/metadc678700

Note

  • Display Note: INIS; OSTI as DE99000395
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