Direct Compositional Characterization of (U,Th)O2 Powders, Microspheres, and Pellets Using TXRF

被引:23
|
作者
Dhara, Sangita [1 ]
Prabhat, Parimal [2 ]
Misra, N. L. [1 ,3 ]
机构
[1] Bhabha Atom Res Ctr, Div Fuel Chem, Bombay 400085, Maharashtra, India
[2] Heavy Water Board, Technol Demonstrat Plant, Bombay 400074, Maharashtra, India
[3] Homi Bhabha Natl Inst, Bombay 400094, Maharashtra, India
关键词
REFLECTION; THORIUM; MICROANALYSIS; OXIDE;
D O I
10.1021/acs.analchem.5b01824
中图分类号
O65 [分析化学];
学科分类号
070302 ; 081704 ;
摘要
A total reflection X-ray fluorescence (TXRF) analysis method for direct compositional characterization of sintered and green (U,Th)O-2 samples in different forms (e.g., pellets, powders, and microspheres) without sample dissolution has been developed for the first time. The methodology involves transfer of only a few nanograms of the sample on the TXRF sample support by gently rubbing the samples on supports or taking their tiny uniform slurry in collodion on the sample support, drying them to make thin film, and measuring the TXRF spectra of the specimens thus prepared. This approach minimizes the matrix effects. Uranium determinations from the TXRF spectra of such specimens were made with respect to thorium, considering it as an internal standard. Samples having uranium atom percent (at%) from 0 to 100 in (U,Th)O-2 were analyzed for uranium in comparison to thorium. The results showed an average precision of 2.6% (RSD, 2 sigma, n = 8). The TXRF-determined results deviated from expected values within 5%. The TXRF results were compared with those of biamperometry with good agreement. The lattice parameters of the solid solutions were calculated using their XRD patterns. A good correlation between lattice parameters and TXRF-determined U at% and between TXRF-determined U at% and expected U at%, calculated on the basis of preparation of (U,Th)O-2 solid solutions, was obtained. The developed method is capable of analyzing (U,Th)O-2 samples directly with almost negligible sample preparation and is well suited for radioactive samples. The present study suggests that this method can be extended for the determination of U,Th and Pu in other nuclear fuel materials (e.g., nitrides, carbides, etc.) in the form of pellets, powders, and microspheres after suitable modifications in sample handling procedure.
引用
收藏
页码:10262 / 10267
页数:6
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