Analysis of a hypothetical dropped spent nuclear fuel shipping cask impacting a floor mounted crush pad Metadata

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Title

  • Main Title Analysis of a hypothetical dropped spent nuclear fuel shipping cask impacting a floor mounted crush pad

Creator

  • Author: Hawkes, B.D.
    Creator Type: Personal
  • Author: Uldrich, E.D.
    Creator Type: Personal

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: Idaho National Engineering and Environmental Laboratory
    Place of Publication: Idaho Falls, Idaho
    Additional Info: Lockheed Martin Idaho Technologies Co., Idaho National Engineering and Environmental Lab., Idaho Falls, ID (United States)

Date

  • Creation: 1998-03-01

Language

  • English

Description

  • Content Description: A crush pad has been designed and analyzed to absorb the kinetic energy of a hypothetically dropped spent nuclear fuel shipping cask into a 44-ft. deep cask unloading pool at the Idaho Chemical Processing Plant. The 110-ton Large Cell Cask was assumed to be accidentally dropped onto the parapet of the unloading pool, causing the cask to tumble through the pool water and impact the floor mounted crush pad with the cask`s top corner. The crush pad contains rigid polyurethane foam, which was modeled in a separate computer analysis to simulate the manufacturer`s testing of the foam and to determine the foam`s stress and strain characteristics. This computer analysis verified that the foam was accurately represented in the analysis to follow. A detailed non-linear, dynamic finite element analysis was then performed on the crush pad and adjacent pool structure to assure that a drop of this massive cask does not result in unacceptable damage to the storage facility. Additionally, verification was made that the crush pad adequately protects the cask from severe impact loading. At impact, the cask has significant vertical, horizontal and rotational velocities. The crush pad absorbs much of the energy of the cask through plastic deformation during primary and secondary impacts. After the primary impact with the crush pad, the cask still has sufficient energy to rebound and rotate until it impacts the pool wall. An assessment is made of the damage to the crush pad and pool wall and of the impact loading on the cask.
  • Physical Description: 9 p.

Subject

  • Keyword: Spent Fuel Casks
  • Keyword: Fuel Storage Pools
  • Keyword: Computerized Simulation
  • STI Subject Categories: 05 Nuclear Fuels
  • Keyword: Materials Handling
  • Keyword: Impact Tests
  • Keyword: Foams
  • Keyword: Finite Element Method
  • Keyword: Shock Absorbers
  • Keyword: Accidents
  • STI Subject Categories: 42 Engineering Not Included In Other Categories

Source

  • Conference: IMACS international conference on computational engineering in systems applications, Lille (France), 8-10 Jul 1996

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: DE98052574
  • Report No.: INEEL/CON--97-01064
  • Report No.: CONF-960708--
  • Grant Number: AC07-94ID13223
  • Office of Scientific & Technical Information Report Number: 650340
  • Archival Resource Key: ark:/67531/metadc712516

Note

  • Display Note: INIS; OSTI as DE98052574
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