Radiation analysis for a generic centralized interim storage facility

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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) to establish the CISF Protected Area, Unrestricted Area, and Restricted Area boundaries. In order to model a large (6000 cask) storage array with a reasonable amount of analysis time and effort, a simplified calculational model was developed for the CISF. The CISF is designed to accommodate several different types of SNF storage systems. In order to simplify the calculation of dose rates from the storage area, the Westinghouse Large PWR Multi-Purpose Canister (MPC) is selected ... continued below

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6 p.

Creation Information

Gillespie, S.G.; Lopez, P. & Eble, R.G. July 1, 1997.

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  • Gillespie, S.G.
  • Lopez, P. TRW Environmental Safety Systems, Inc., Vienna, VA (United States)
  • Eble, R.G. Duke Engineering and Services, Inc., Charlotte, NC (United States)

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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) to establish the CISF Protected Area, Unrestricted Area, and Restricted Area boundaries. In order to model a large (6000 cask) storage array with a reasonable amount of analysis time and effort, a simplified calculational model was developed for the CISF. The CISF is designed to accommodate several different types of SNF storage systems. In order to simplify the calculation of dose rates from the storage area, the Westinghouse Large PWR Multi-Purpose Canister (MPC) is selected as a representative storage system, since sufficient information is contained in its Safety Analysis Report to allow accurate modeling, and the surface dose rates on the MPC are consistent with other storage systems.

Physical Description

6 p.

Notes

INIS; OSTI as DE97006621

Source

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

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  • Other: DE97006621
  • Report No.: DOE/RW/00134--M97-006
  • Report No.: CONF-971125--1
  • Grant Number: AC01-91RW00134
  • Office of Scientific & Technical Information Report Number: 537247
  • Archival Resource Key: ark:/67531/metadc695803

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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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Creation Date

  • July 1, 1997

Added to The UNT Digital Library

  • Aug. 14, 2015, 8:43 a.m.

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  • May 18, 2016, 5:53 p.m.

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Gillespie, S.G.; Lopez, P. & Eble, R.G. Radiation analysis for a generic centralized interim storage facility, article, July 1, 1997; United States. (digital.library.unt.edu/ark:/67531/metadc695803/: accessed December 11, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.