Gross Gamma Dose Rate Measurements for TRIGA Spent Nuclear Fuel Burnup Validation

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Gross gamma-ray dose rates from six spent TRIGA fuel elements were measured and compared to calculated values as a means to validate the reported element burnups. A newly installed and functional gamma-ray detection subsystem of the In-Cell Examination System was used to perform the measurements and is described in some detail. The analytical methodology used to calculate the corresponding dose rates is presented along with the calculated values. Comparison of the measured and calculated dose rates for the TRIGA fuel elements indicates good agreement (less than a factor of 2 difference). The intent of the subsystem is to measure the ... continued below

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Winston, Philip Lon & Sterbentz, James William April 1, 2001.

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Description

Gross gamma-ray dose rates from six spent TRIGA fuel elements were measured and compared to calculated values as a means to validate the reported element burnups. A newly installed and functional gamma-ray detection subsystem of the In-Cell Examination System was used to perform the measurements and is described in some detail. The analytical methodology used to calculate the corresponding dose rates is presented along with the calculated values. Comparison of the measured and calculated dose rates for the TRIGA fuel elements indicates good agreement (less than a factor of 2 difference). The intent of the subsystem is to measure the gross gamma dose rate and correlate the measurement to a calculated dose rate based on the element s known burnup and other pertinent spent fuel information. Although validation of the TRIGA elements’ burnup is of primary concern in this paper, the measurement and calculational techniques can be used to either validate an element’s reported burnup or provide a burnup estimate for an element with an unknown burnup.

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  • 10th International Conference on Nuclear Energy (ICONE-10),Arlington, VA,04/14/2001,04/18/2001

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  • Report No.: INEEL/CON-01-01615
  • Grant Number: DE-AC07-99ID-13727
  • Office of Scientific & Technical Information Report Number: 910855
  • Archival Resource Key: ark:/67531/metadc880680

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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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  • April 1, 2001

Added to The UNT Digital Library

  • Sept. 22, 2016, 2:13 a.m.

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  • Dec. 9, 2016, 4:48 p.m.

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Winston, Philip Lon & Sterbentz, James William. Gross Gamma Dose Rate Measurements for TRIGA Spent Nuclear Fuel Burnup Validation, article, April 1, 2001; [Idaho Falls, Idaho]. (digital.library.unt.edu/ark:/67531/metadc880680/: accessed July 21, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.