Non-destructive analysis of low-enriched and natural U samples by γ-spectrometry
2003
Abstract Passive non-destructive assay methods were employed for quantitative analysis of low-enriched, natural, and depleted uranium-containing reactor fuel pellets of unknown origin and powder-form chemicals, using high-resolution γ-ray spectrometry. The isotopic composition and the amount of 238 U were determined applying intrinsic calibration and attenuation correction methods, respectively. The 238 U mass was measured by a relative method, using a certified reference set for calibration. After finding the total U-content, the matrix of the samples (UO 2 , U 3 O 8 , uranyl-acetate, and uranyl-nitrate) was also identified for material without cladding.
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