Determination of Light Water Reactor Fuel Burnup with the Isotope Ratio Method

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For the current project to demonstrate that isotope ratio measurements can be extended to zirconium alloys used in LWR fuel assemblies we report new analyses on irradiated samples obtained from a reactor. Zirconium alloys are used for structural elements of fuel assemblies and for the fuel element cladding. This report covers new measurements done on irradiated and unirradiated zirconium alloys, Unirradiated zircaloy samples serve as reference samples and indicate starting values or natural values for the Ti isotope ratio measured. New measurements of irradiated samples include results for 3 samples provided by AREVA. New results indicate: 1. Titanium isotope ratios ... continued below

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Gerlach, David C.; Mitchell, Mark R.; Reid, Bruce D.; Gesh, Christopher J. & Hurley, David E. November 1, 2007.

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For the current project to demonstrate that isotope ratio measurements can be extended to zirconium alloys used in LWR fuel assemblies we report new analyses on irradiated samples obtained from a reactor. Zirconium alloys are used for structural elements of fuel assemblies and for the fuel element cladding. This report covers new measurements done on irradiated and unirradiated zirconium alloys, Unirradiated zircaloy samples serve as reference samples and indicate starting values or natural values for the Ti isotope ratio measured. New measurements of irradiated samples include results for 3 samples provided by AREVA. New results indicate: 1. Titanium isotope ratios were measured again in unirradiated samples to obtain reference or starting values at the same time irradiated samples were analyzed. In particular, 49Ti/48Ti ratios were indistinguishably close to values determined several months earlier and to expected natural values. 2. 49Ti/48Ti ratios were measured in 3 irradiated samples thus far, and demonstrate marked departures from natural or initial ratios, well beyond analytical uncertainty, and the ratios vary with reported fluence values. The irradiated samples appear to have significant surface contamination or radiation damage which required more time for SIMS analyses. 3. Other activated impurity elements still limit the sample size for SIMS analysis of irradiated samples. The sub-samples chosen for SIMS analysis, although smaller than optimal, were still analyzed successfully without violating the conditions of the applicable Radiological Work Permit

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  • Report No.: PNNL-17053 Vol 1
  • Grant Number: AC05-76RL01830
  • DOI: 10.2172/1006337 | External Link
  • Office of Scientific & Technical Information Report Number: 1006337
  • Archival Resource Key: ark:/67531/metadc835670

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Office of Scientific & Technical Information Technical Reports

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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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  • November 1, 2007

Added to The UNT Digital Library

  • May 19, 2016, 3:16 p.m.

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  • Dec. 5, 2016, 2 p.m.

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Gerlach, David C.; Mitchell, Mark R.; Reid, Bruce D.; Gesh, Christopher J. & Hurley, David E. Determination of Light Water Reactor Fuel Burnup with the Isotope Ratio Method, report, November 1, 2007; Richland, Washington. (digital.library.unt.edu/ark:/67531/metadc835670/: accessed July 19, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.