Radiation analysis for a generic centralized interim storage facility Metadata

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Title

  • Main Title Radiation analysis for a generic centralized interim storage facility

Creator

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

Contributor

  • Sponsor: United States. Department of Energy. Office of Civilian Radioactive Waste Management.
    Contributor Type: Organization
    Contributor Info: USDOE Office of Civilian Radioactive Waste Management, Washington, DC (United States)

Publisher

  • Name: TRW Environmental Safety Systems, Inc.
    Place of Publication: Vienna, Virginia

Date

  • Creation: 1997-07-01

Language

  • English

Description

  • Content 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.

Subject

  • STI Subject Categories: 56 Biology And Medicine, Applied Studies
  • Keyword: Spent Fuel Storage
  • STI Subject Categories: 05 Nuclear Fuels
  • Keyword: Mathematical Models
  • Keyword: Calculation Methods
  • Keyword: Spent Fuel Casks
  • Keyword: Storage Facilities
  • Keyword: Radiation Doses

Source

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

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: 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

Note

  • Display Note: INIS; OSTI as DE97006621