Buckling analysis of spent fuel basket Metadata

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  • Main Title Buckling analysis of spent fuel basket


  • Author: Lee, A.S.
    Creator Type: Personal
  • Author: Bumpas, S.E.
    Creator Type: Personal
    Creator Info: Lawrence Livermore National Lab., CA (United States)


  • Sponsor: U.S. Nuclear Regulatory Commission
    Contributor Type: Organization
    Contributor Info: Nuclear Regulatory Commission, Washington, DC (United States)


  • Name: Nuclear Regulatory Commission, Washington, DC (United States). Div. of Industrial and Medical Nuclear Safety
    Place of Publication: United States
  • Name: Lawrence Livermore National Laboratory
    Place of Publication: California
    Additional Info: Lawrence Livermore National Lab., CA (United States)


  • Creation: 1995-05-01


  • English


  • Content Description: The basket for a spent fuel shipping cask is subjected to compressive stresses that may cause global instability of the basket assemblies or local buckling of the individual members. Adopting the common buckling design practice in which the stability capacity of the entire structure is based on the performance of the individual members of the assemblies, the typical spent fuel basket, which is composed of plates and tubular structural members, can be idealized as an assemblage of columns, beam-columns and plates. This report presents the flexural buckling formulas for five load cases that are common in the basket buckling analysis: column under axial loads, column under axial and bending loads, plate under uniaxial loads, plate under biaxial loadings, and plate under biaxial loads and lateral pressure. The acceptance criteria from the ASME Boiler and Pressure Vessel Code are used to determine the adequacy of the basket components. Special acceptance criteria are proposed to address the unique material characteristics of austenitic stainless steel, a material which is frequently used in the basket assemblies.
  • Physical Description: 45 p.


  • Keyword: Flexural Strength
  • Keyword: Austenitic Steels
  • STI Subject Categories: 36 Materials Science
  • Keyword: Standards
  • STI Subject Categories: 05 Nuclear Fuels
  • Keyword: Calculation Methods
  • Keyword: Spent Fuel Casks
  • Keyword: Spent Fuels
  • Keyword: Design
  • Keyword: Accidents
  • Keyword: Deformation
  • Keyword: Transport
  • STI Subject Categories: 42 Engineering Not Included In Other Categories
  • Keyword: Fuel Racks


  • Other Information: PBD: May 1995


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


  • Name: UNT Libraries Government Documents Department
    Code: UNTGD

Resource Type

  • Report


  • Text


  • Other: TI95011867
  • Report No.: NUREG/CR--6322
  • Report No.: UCRL-ID--119697
  • Grant Number: W-7405-ENG-48
  • DOI: 10.2172/71376
  • Office of Scientific & Technical Information Report Number: 71376
  • Archival Resource Key: ark:/67531/metadc707848


  • Display Note: INIS; OSTI as TI95011867