Utilization of a finite element model to verify spent nuclear fuel storage rack welds

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Elastic and plastic finite element analyses were performed for the inner tie block assembly of a 25 port fuel rack designed for installation at the Idaho National Engineering and Environmental Laboratory (INEEL) Idaho Chemical Processing Plant (ICPP). The model was specifically developed to verify the adequacy of certain welds joining components of the fuel storage rack assembly. The work scope for this task was limited to an investigation of the stress levels in the inner tie welds when the rack was subjected to seismic loads. Structural acceptance criteria used for the elastic calculations performed were as defined by the rack`s ... continued below

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12 p.

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Nitzel, M.E. July 1, 1998.

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Description

Elastic and plastic finite element analyses were performed for the inner tie block assembly of a 25 port fuel rack designed for installation at the Idaho National Engineering and Environmental Laboratory (INEEL) Idaho Chemical Processing Plant (ICPP). The model was specifically developed to verify the adequacy of certain welds joining components of the fuel storage rack assembly. The work scope for this task was limited to an investigation of the stress levels in the inner tie welds when the rack was subjected to seismic loads. Structural acceptance criteria used for the elastic calculations performed were as defined by the rack`s designer. Structural acceptance criteria used for the plastic calculations performed as part of this effort were as defined in Subsection NF and Appendix F of Section III of the ASME Boiler and Pressure Vessel Code. The results confirm that the welds joining the inner tie block to the surrounding rack structure meet the acceptance criteria. The analysis results verified that the inner tie block welds should be capable of transferring the expected seismic load without structural failure.

Physical Description

12 p.

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INIS; OSTI as DE98057368

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  • 1998 ASME/JSME joint pressure vessel and piping (PVP) conference, San Diego, CA (United States), 26-30 Jul 1998

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  • Other: DE98057368
  • Report No.: INEEL/CON--98-00276
  • Report No.: CONF-980708--
  • Grant Number: AC07-94ID13223
  • Office of Scientific & Technical Information Report Number: 663442
  • Archival Resource Key: ark:/67531/metadc710196

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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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  • July 1, 1998

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  • Sept. 12, 2015, 6:31 a.m.

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  • June 14, 2016, 1:19 p.m.

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Nitzel, M.E. Utilization of a finite element model to verify spent nuclear fuel storage rack welds, article, July 1, 1998; Idaho Falls, Idaho. (digital.library.unt.edu/ark:/67531/metadc710196/: accessed July 21, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.