Determination of uranium content in ammonium uranyl carbonate (AUC) and triuranium octoxide (U3O8)

被引:5
|
作者
Dobrev, Lyuben [1 ]
Nonova, Tzvetana [1 ]
机构
[1] Bulgarian Acad Sci, Inst Nucl Res & Nucl Energy, 72 Tzarigradsko Chaussee, Sofia 1784, Bulgaria
关键词
Ammonium uranyl carbonate; Uranium; U3O8; Co-precipitation; Alpha-spectrometry; ICP-MS; ALPHA; PRECIPITATION; SPECTROMETRY; SEPARATION; ACTINIDES; RECOVERY; THORIUM; ORES;
D O I
10.1007/s10967-020-07471-4
中图分类号
O65 [分析化学];
学科分类号
070302 ; 081704 ;
摘要
This paper presents a fast and reproducible method for determination of uranium content in ammonium uranyl carbonate (AUC) and U3O8 obtained from it. The effects of high activity and specific chemical composition of the samples were minimized by adapting the radiochemical procedures for analysis of a small amount of samples. Measurements were made by alpha-spectrometry and ICP-MS. The results show that the applied procedures are stable with significant yield and can be successfully used for analysis of AUC and U3O8. Comparison of the data obtained by alpha-spectrometry and by ICP-MS shows that the measured values are in good coincidence.
引用
收藏
页码:1543 / 1550
页数:8
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