Non-destructive analysis of low-enriched and natural U samples by γ-spectrometry

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 238U were determined applying intrinsic calibration and attenuation correction methods, respectively. The 238U 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 (UO2, U3O8, uranyl-acetate, and uranyl-nitrate) was also identified for material without cladding.