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Non-destructive determination of uranium and plutonium in annular (U, Pu)O2 mixed oxide sintered pellets by wavelength dispersive X-ray fluorescence spectrometry
Journal of Radioanalytical and Nuclear Chemistry ( IF 1.5 ) Pub Date : 2020-08-05 , DOI: 10.1007/s10967-020-07309-z
A. Pandey , F. A. Khan , A. Kelkar , P. Purohit , Pradeep Kumar , Vijay Kumar , D. B. Sathe , R. B. Bhatt , P. G. Behere

A non-destructive wavelength dispersive X-ray fluorescence (WDXRF) spectrometric method for direct determination of uranium and plutonium in as fabricated annular sintered (U, Pu)O2 mixed oxide (MOX) pellets avoiding the traditional cumbersome sample preparation involving dissolution or comminution–pelletization of sample has been developed. Sintered (U, Pu)O2 MOX pellets were directly analyzed using this method by taking the sample pellets inside an indigenously developed special collet which was loaded in the spectrometer for WDXRF measurements. The developed methodology has the utility for regular analysis of samples in fuel fabrication facilities. The relative standard deviation of the analytical results for U and Pu using WDXRF were found to be better than ± 0.13% and ± 0.31% (n = 10) respectively and equivalent plutonium content obtained are in close agreement with the standard titrimetric methods.

中文翻译:

波长色散X射线荧光光谱法无损测定环形(U,Pu)O2混合氧化物烧结球团中的铀和钚

一种非破坏性波长色散 X 射线荧光 (WDXRF) 光谱法,用于直接测定制成的环形烧结 (U, Pu)O2 混合氧化物 (MOX) 小球中的铀和钚,避免了传统的涉及溶解或粉碎的繁琐样品制备——已经开发了样品的造粒。使用这种方法直接分析烧结的 (U, Pu) O2 MOX 颗粒,方法是将样品颗粒放入自行开发的特殊夹头中,该夹头装入光谱仪进行 WDXRF 测量。所开发的方法可用于定期分析燃料制造设施中的样品。发现使用 WDXRF 的 U 和 Pu 分析结果的相对标准偏差优于 ± 0.13% 和 ± 0。
更新日期:2020-08-05
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