Journal of Nuclear Materials
ISSN: 0022-3115
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Datasets associated with articles published in Journal of Nuclear Materials
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Thermal diffusivity data of uranium, uranium 5 mass% zirconium, and uranium 5 mass% zirconium. Data collected from a Netzsch 447 from 20C to 300C using the Cape Lehman model with pulse correction. Solid samples and samples with porosity up to approximately 70% are included.
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This data is from the electrolytic oxide reduction of uranium oxide in LiCl-Li2O at 650 C. The goal of these tests were to elucidate Li2O entrainment behavior with respect to changes in process variables. Several reductions and associated characterizations are contained including titration, TGA, and SEM data.
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Weak and Strong Isotherm data collected for eight amorphous carbon materials
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  • Tabular Data
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X-ray diffraction data
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Supplementary Information
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Material properties of welded FeCrAl alloys before and after heat treatment
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  • Document
Post weld heat treatment data for laser welds of FeCrAl alloys.
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  • Document
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