Radiation analysis for a generic centralized interim storage facility

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This paper documents the radiation analysis performed for the storage area of a generic Centralized Interim Storage Facility (CISF) for commercial spent nuclear fuel (SNF). The purpose of the analysis is to establish the CISF Protected Area and Restricted Area boundaries by modeling a representative SNF storage array, calculating the radiation dose at selected locations outside the storage area, and comparing the results with regulatory radiation dose limits. The particular challenge for this analysis is to adequately model a large (6000 cask) storage array with a reasonable amount of analysis time and effort. Previous analyses of SNF storage systems for ... continued below

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14 p.

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Gillespie, S. G.; Lopez, P. & Eble, R. G. December 31, 1997.

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Description

This paper documents the radiation analysis performed for the storage area of a generic Centralized Interim Storage Facility (CISF) for commercial spent nuclear fuel (SNF). The purpose of the analysis is to establish the CISF Protected Area and Restricted Area boundaries by modeling a representative SNF storage array, calculating the radiation dose at selected locations outside the storage area, and comparing the results with regulatory radiation dose limits. The particular challenge for this analysis is to adequately model a large (6000 cask) storage array with a reasonable amount of analysis time and effort. Previous analyses of SNF storage systems for Independent Spent Fuel Storage Installations at nuclear plant sites (for example in References 5.1 and 5.2) had only considered small arrays of storage casks. For such analyses, the dose contribution from each storage cask can be modeled individually. Since the large number of casks in the CISF storage array make such an approach unrealistic, a simplified model is required.

Physical Description

14 p.

Notes

INIS; OSTI as DE97000797

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  • 1997 American Nuclear Society (ANS) winter meeting, Albuquerque, NM (United States), 16-20 Nov 1997

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  • Other: DE97000797
  • Report No.: DOE/RW/00134--M97-011
  • Report No.: CONF-971125--
  • Grant Number: AC01-91RW00134
  • Office of Scientific & Technical Information Report Number: 574260
  • Archival Resource Key: ark:/67531/metadc689578

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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.

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  • December 31, 1997

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  • Aug. 14, 2015, 8:43 a.m.

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  • April 10, 2018, 2:13 p.m.

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Gillespie, S. G.; Lopez, P. & Eble, R. G. Radiation analysis for a generic centralized interim storage facility, article, December 31, 1997; Vienna, Virginia. (digital.library.unt.edu/ark:/67531/metadc689578/: accessed December 18, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.