Actions for Determination of Light Water Reactor Fuel Burnup with the Isotope Ratio Method [electronic resource].

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Determination of Light Water Reactor Fuel Burnup with the Isotope Ratio Method [electronic resource].

Published
Washington, D.C. : United States. Dept. of Energy, 2007.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description
PDFN
Additional Creators
Pacific Northwest National Laboratory (U.S.), United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
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
Report Numbers
E 1.99:pnnl-17053 vol 1
pnnl-17053 vol 1
Subject(s)
Other Subject(s)
Note
Published through SciTech Connect.
11/01/2007.
"pnnl-17053 vol 1"
"NN2001000"
Gerlach, David C.; Gesh, Christopher J.; Hurley, David E.; Mitchell, Mark R.; Reid, Bruce D.
Funding Information
AC05-76RL01830
View MARC record | catkey: 14450076