Simulations of self- and Xe diffusivity in uranium mononitride including chemistry and irradiation effects

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
M.W.D. Cooper , J. Rizk , C. Matthews , V. Kocevski , G.T. Craven , T. Gibson , D.A. Andersson
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Abstract

A combination of density functional theory and empirical potential atomic scale simulations have been used to determine a model for defect stability and mobility in uranium mononitride (UN), as a function of temperature (T) and N2 partial pressure (pN2). Using the model, predictions of hypo-stoichiometry under U-rich conditions compare favorably to CALPHAD calculations using the TAF-ID database. Furthermore, our predictions of U and N self-diffusivity are in good agreement with experiments carried out as a function of T at specific partial pressures under thermal equilibrium. The validated atomic scale data have then been implemented within a cluster dynamics method to simulate irradiation-enhanced defect concentrations. All defects and clusters studied have significantly enhanced concentrations, with respect to thermal equilibrium, as T is lowered. The irradiation-enhanced Xe diffusivity is compared to post-irradiation annealing and in-pile experiments. The contributions of various defects and clusters to non-stoichiometry, self-diffusivity, and Xe diffusivity are discussed.

含化学和辐照效应的一氮化铀自扩散率和Xe扩散率的模拟
采用密度泛函理论和经验势原子尺度模拟相结合的方法,建立了单氮化铀(UN)中缺陷稳定性和迁移率随温度(T)和N2分压(pN2)的函数模型。使用该模型,富铀条件下的低化学计量预测比使用TAF-ID数据库的CALPHAD计算更有利。此外,我们对U和N自扩散率的预测与热平衡下比分压下T的函数的实验结果很好地吻合。经过验证的原子尺度数据随后在簇动力学方法中实现,以模拟辐照增强的缺陷浓度。随着温度的降低,所研究的所有缺陷和团簇的热平衡浓度都显著提高。将辐照增强的Xe扩散系数与辐照后退火和堆内实验进行了比较。讨论了各种缺陷和团簇对非化学计量、自扩散率和Xe扩散率的贡献。
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来源期刊
Journal of Nuclear Materials
Journal of Nuclear Materials 工程技术-材料科学:综合
CiteScore
5.70
自引率
25.80%
发文量
601
审稿时长
63 days
期刊介绍: The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.
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