ANL calculational methodologies for determining spent nuclear fuel source term

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Description

Over the last decade Argonne National Laboratory has developed reactor depletion methods and models to determine radionuclide inventories of irradiated EBR-II fuels. Predicted masses based on these calculational methodologies have been validated using available data from destructive measurements--first from measurements of lead EBR-II experimental test assemblies and later using data obtained from processing irradiated EBR-II fuel assemblies in the Fuel Conditioning Facility. Details of these generic methodologies are described herein. Validation results demonstrate these methods meet the FCF operations and material control and accountancy requirements.

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9 p.

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McKnight, R. D. March 24, 2000.

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This article is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 30 times . More information about this article can be viewed below.

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  • Argonne National Laboratory
    Publisher Info: Argonne National Laboratory, Argonne, IL (United States)
    Place of Publication: Argonne, Illinois

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Description

Over the last decade Argonne National Laboratory has developed reactor depletion methods and models to determine radionuclide inventories of irradiated EBR-II fuels. Predicted masses based on these calculational methodologies have been validated using available data from destructive measurements--first from measurements of lead EBR-II experimental test assemblies and later using data obtained from processing irradiated EBR-II fuel assemblies in the Fuel Conditioning Facility. Details of these generic methodologies are described herein. Validation results demonstrate these methods meet the FCF operations and material control and accountancy requirements.

Physical Description

9 p.

Notes

INIS; OSTI as DE00752906

Medium: P; Size: 9 pages

Source

  • ANS 4th Topical Meeting - DOE Spent Nuclear Fuel and Fissile Material Management, San Diego, CA (US), 06/04/2000--06/08/2000

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  • Report No.: ANL/RA/CP-101396
  • Grant Number: W-31109-ENG-38
  • Office of Scientific & Technical Information Report Number: 752906
  • Archival Resource Key: ark:/67531/metadc709106

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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

  • March 24, 2000

Added to The UNT Digital Library

  • Sept. 12, 2015, 6:31 a.m.

Description Last Updated

  • April 11, 2017, 7:29 p.m.

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McKnight, R. D. ANL calculational methodologies for determining spent nuclear fuel source term, article, March 24, 2000; Argonne, Illinois. (digital.library.unt.edu/ark:/67531/metadc709106/: accessed June 22, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.