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

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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 ... continued below

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9 p.

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Hawkes, B.D. & Uldrich, E.D. March 1, 1998.

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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.

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9 p.

Notes

INIS; OSTI as DE98052574

Source

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

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  • 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

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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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  • March 1, 1998

Added to The UNT Digital Library

  • Sept. 12, 2015, 6:31 a.m.

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  • June 13, 2016, 6:38 p.m.

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Hawkes, B.D. & Uldrich, E.D. Analysis of a hypothetical dropped spent nuclear fuel shipping cask impacting a floor mounted crush pad, article, March 1, 1998; Idaho Falls, Idaho. (digital.library.unt.edu/ark:/67531/metadc712516/: accessed July 20, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.