A preliminary evaluation of certain NDA techniques for RH-TRU characterization

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This report presents the results of modeling efforts to evaluate selected NDA assay methods for RH-TRU waste characterization. The target waste stream was Content Code 104/107 113-liter waste drums that comprise the majority of the INEL`s RH-TRU waste inventory. Two NDA techniques are treated in detail. One primary NDA technique examined is gamma-ray spectrometry to determine the drum fission and activation product content, and fuel sample inventory calculations using the ORIGEN code to predict the total drum inventory. A heavily shielded and strongly collimated HPGE spectrometer system was designed using MCNP modeling. Detection limits and expected precision of this approach ... continued below

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22 p.

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Hartwell, J. K.; Yoon, W. Y. & Peterson, H. K. December 1996.

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Description

This report presents the results of modeling efforts to evaluate selected NDA assay methods for RH-TRU waste characterization. The target waste stream was Content Code 104/107 113-liter waste drums that comprise the majority of the INEL`s RH-TRU waste inventory. Two NDA techniques are treated in detail. One primary NDA technique examined is gamma-ray spectrometry to determine the drum fission and activation product content, and fuel sample inventory calculations using the ORIGEN code to predict the total drum inventory. A heavily shielded and strongly collimated HPGE spectrometer system was designed using MCNP modeling. Detection limits and expected precision of this approach were estimated by a combination of Monte Carlo modeling and synthetic gamma-ray spectrum generation. This technique may allow the radionuclide content of these wastes to be determined with relative standard deviations of 20 to 55% depending on the drum matrix and radionuclide. The INEL Passive/Active Neutron (PAN) assay system is the second primary technique considered. A shielded overpack for the 113-liter CC104/107 RH-TRU drums was designed to shield the PAN detectors from excessive gamma radiation. MCNP modeling suggests PAN detection limits of about 0.06 g {sup 235}U and 0.04 g {sup 239}Pu during active assays.

Physical Description

22 p.

Notes

INIS; OSTI as DE97052148

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  • 5. nondestructive assay/nondestructive examination waste characterization conference, Salt Lake City, UT (United States), 14-16 Jan 1997

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  • Other: DE97052148
  • Report No.: INEL--96/00295
  • Report No.: CONF-970126--16
  • Grant Number: AC07-94ID13223
  • Office of Scientific & Technical Information Report Number: 495684
  • Archival Resource Key: ark:/67531/metadc678873

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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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  • December 1996

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  • July 25, 2015, 2:21 a.m.

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  • June 14, 2016, 3:57 p.m.

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Hartwell, J. K.; Yoon, W. Y. & Peterson, H. K. A preliminary evaluation of certain NDA techniques for RH-TRU characterization, article, December 1996; Idaho Falls, Idaho. (digital.library.unt.edu/ark:/67531/metadc678873/: accessed May 20, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.