2016
DOI: 10.1016/j.corsci.2016.05.036
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The crystallographic structure of the air-grown oxide on depleted uranium metal

Abstract: General rightsThis document is made available in accordance with publisher policies. Please cite only the published version using the reference above. Full terms of use are available: http://www.bristol.ac.uk/pure/about/ebr-termsThe crystallographic structure of the air-grown oxide on depleted uranium metal AbstractOxide formation on depleted uranium metal was investigated using a combination of electron backscatter diffraction (EBSD) and transmission electron microscopy (TEM) characterisation. Diffraction an… Show more

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Cited by 19 publications
(6 citation statements)
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References 30 publications
(46 reference statements)
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“…In most metallic nuclear materials, either only a very small dependence of the oxidation behaviour on different substrate orientations was found, e.g. in zirconium alloys [29], or in some cases, no variation at all was found, as is the case for uranium [30]. On the other hand, in non-metallic compounds such as uranium dioxide [31] a marked orientational dependence on aqueous dissolution was observed.…”
Section: Introductionmentioning
confidence: 99%
“…In most metallic nuclear materials, either only a very small dependence of the oxidation behaviour on different substrate orientations was found, e.g. in zirconium alloys [29], or in some cases, no variation at all was found, as is the case for uranium [30]. On the other hand, in non-metallic compounds such as uranium dioxide [31] a marked orientational dependence on aqueous dissolution was observed.…”
Section: Introductionmentioning
confidence: 99%
“…On the experimental U metal samples contacting humid atmospheres and water solutions, the hydration phenomenon ubiquitously takes place and considerably promotes the environmental degradation process of the native oxide films, especially at the reactive grainboundary sites. 3,5,8,10,11,14 Such a hydration process occurring at defect sites and its corrosion promoting effect can be understood more clearly by illustrating a similar example with the prototypical α-Al 2 O 3 . The compact corundum crystal structure of α-Al 2 O 3 films can provide superior protection to many metal and coating substrates in regular environments.…”
Section: = | |=mentioning
confidence: 98%
“…It is the spontaneously formed oxide films that serve as the native corrosion barriers for the metal substrates because of the reduced surface adsorption and blocked defect permeation. , Thus, in various chemical and mechanical treatment methods (e.g., alloying and ultrasonic surface rolling) that can obviously improve the corrosion resistance of actinide metals, , the key mechanisms are always associated with the optimized microscopic states of the native oxide films. The environmental water molecules may aggravate the breakdown of oxide films through accelerating the surface electrochemical reactions on these native outer-layer oxide films and then forming loose and pyrophoric hydrides at the oxide/metal interfaces. ,, Apart from serving as the protective films on actinide metals, actinide oxides themselves are the major chemical forms for nuclear fission fuels. The traditional fuels mainly consist of UO 2 , plus some possible oxidization byproducts (e.g., U 4 O 9 , U 3 O 7 , U 3 O 8 , and UO 3 ). ,,, Mixed-oxide fuels consisting of UO 2 and PuO 2 powders have also been developed for the new-generation fast breeder reactors, making it possible to dispose the industrial and military Pu in a more sustainable recycling approach. , The thermodynamic oxidations of UO 2 and PuO 2 under an environment, if not precisely predicted and appropriately controlled, will bring unexpected volume expansion and stress accumulation.…”
Section: Introductionmentioning
confidence: 99%
“…In addition, UO 2 is the main product of the uranium oxidation reaction . Experimental findings reveal that the layer of uranium oxide formed in air consists of UO 2 nano-grains, averaging around 12 nm in grain size . The oxidation of uranium, being a diffusion-controlled process, is governed by the rate of oxygen diffusion through the defects, especially GBs, existing in the oxide layers. , Therefore, gaining a deep understanding of the characteristics of UO 2 GBs is vital for predicting fuel performance, safety, and longevity, as well as for elucidating and regulating uranium corrosion.…”
Section: Introductionmentioning
confidence: 99%