Image fusion of Secondary Ion Mass Spectrometry and Energy-dispersive X-Ray Spectroscopy data for the characterization of uranium-molybdenum fuel foils

被引:1
|
作者
Willingham, David [1 ]
Naes, Benjamin E. [1 ]
Tarolli, Jay G. [1 ]
Schemer-Kohrn, Alan [1 ]
Rhodes, Mark [1 ]
Dahl, Michael [1 ]
Guzman, Anthony [1 ]
Burkes, Douglas E. [1 ]
机构
[1] Pacific Northwest Natl Lab, 902 Battelle Blvd, Richland, WA 99352 USA
关键词
U-MO; NUCLEAR; ALLOY;
D O I
10.1016/j.jnucmat.2017.10.028
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Uranium-molybdenum (U-Mo) monolithic fuels represent one option for converting civilian research and test reactors operating with high enriched uranium (HEU) to low enriched uranium (LEU), effectively reducing the threat of nuclear proliferation world-wide. However, processes associated with fabrication of U-Mo monolithic fuels result in regions of elemental heterogeneity, observed as bands traversing the cross-section of representative samples. Isotopic variations (e.g., U-235 and U-238) could also be introduced because of associated processing steps, particularly since HEU feedstock is melted with natural or depleted uranium diluent to produce LEU. This study demonstrates the utility of correlative analysis of Energy-Dispersive X-ray Spectroscopy (EDS) and Secondary Ion Mass Spectrometry (SIMS) with their image data streams using image fusion, resulting in a comprehensive microanalytical characterization toolbox. Elemental and isotopic measurements were made on a sample from the Advanced Test Reactor (ATR) Full-sized plate In-center flux trap Position (AFIP)-7 experiment and compared to previous optical and electron microscopy results. The image fusion results are characteristic of SIMS isotopic maps, but with the spatial resolution of EDS images and, therefore, can be used to increase the effective spatial resolution of the SIMS imaging results to better understand homogeneity or heterogeneity that persists because of processing selections. Visual inspection using the image fusion methodology indicated slight variations in the 235U/238U ratio and quantitative analysis using the image intensities across several FoVs revealed an average 235U atom percent value of 17.9 +/- 2.4%, which was indicative of a non-uniform U isotopic distribution in the area sampled. Further development of this capability is useful for understanding the connections between the properties of LEU fuel alternatives and the ability to predict performance under irradiation. (C) 2017 Elsevier B.V. All rights reserved.
引用
收藏
页码:348 / 354
页数:7
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