首页> 外文期刊>Inorganic Chemistry: A Research Journal that Includes Bioinorganic, Catalytic, Organometallic, Solid-State, and Synthetic Chemistry and Reaction Dynamics >New Insight into Self-Irradiation Effects on Local and Long-Range Structure of Uranium?Americium Mixed Oxides (through XAS and XRD)
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New Insight into Self-Irradiation Effects on Local and Long-Range Structure of Uranium?Americium Mixed Oxides (through XAS and XRD)

机译:自辐照对铀?混合氧化物局部和远距离结构的影响的新见解(通过XAS和XRD)

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摘要

Uranium?americium mixed oxides could be used as transmutation targets to lower Am inventory in spent nuclear fuels. Due to ~(241)Am activity, these materials are subjected to α-selfirradiation which provokes crystallographic disorder. Previous studies on U?Am mixed oxides gave first insight into α-radiation tolerance of these compounds, but have never been carried out for more than a year, whereas these compounds might be stored up to a few years between fabrication and irradiation. In this work, we study effects of self-irradiation on the structure of U_(1?x)Am_xO_(2±δ) solid solutions (x = 0.15 and 0.20) aged 3 to 4 years. Especially, Xray diffraction and X-ray absorption spectroscopy are combined to observe these effects from both long-range and local perspectives. Results show that the fluorite-type structure of U?Am mixed oxides withstands ~(241)Am α-irradiation without major damage. Despite the increase of interatomic distances and crystallographic disorder observed during the first months of storage, the present results show that a steady state is then reached. Thus, no detrimental factors have been identified in this study in terms of structural damage for several-year storage of U_(1?x)Am_xO_(2±δ) pellets before irradiation. Furthermore, comparison between long-range and local evolution suggests that α-self-irradiationinduced defects are mainly located in low-ordered domains. Based on literature data and present results, the steady state appears related to the equilibrium between radioinduced defect formation and material self-healing.
机译:铀?混合氧化物可以用作trans变目标,以降低乏核燃料中的Am存量。由于〜(241)Am的活性,这些材料受到α-自辐照,从而引起晶体学紊乱。先前对U?Am混合氧化物的研究首次了解了这些化合物的α辐射耐受性,但是从未进行超过一年的研究,而这些化合物在制造和辐照之间可能保存长达数年。在这项工作中,我们研究了3至4岁时自辐照对U_(1?x)Am_xO_(2±δ)固溶体(x = 0.15和0.20)的结构的影响。尤其是,将X射线衍射和X射线吸收光谱法结合起来可以从远距离和局部角度观察这些影响。结果表明,U?Am混合氧化物的萤石型结构能承受〜(241)Amα辐照,而不会造成重大损害。尽管在存储的头几个月中观察到了原子间距离的增加和晶体学紊乱,但目前的结果表明,随后达到了稳定状态。因此,在本研究中没有发现有害的因素,即辐照前U_(1?x)Am_xO_(2±δ)颗粒的数年贮存对结构的损害。此外,在远距离和局部演化之间的比较表明,α-自辐照引起的缺陷主要位于低序域。根据文献数据和目前的结果,稳态似乎与放射性缺陷形成和材料自愈之间的平衡有关。

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