关于UO2中颗粒内气泡的捕获和再溶解模型,与原子尺度模拟相关联

IF 3.2 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2025-02-01 Epub Date: 2024-12-10 DOI:10.1016/j.jnucmat.2024.155562
M. Vergani , M.W.D. Cooper , L. Noirot
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引用次数: 0

摘要

在文献中,没有明确定义UO2燃料中气泡气体的辐照再溶解频率。此外,对于颗粒内气泡,在再溶解事件发生后,累积位移气体量与气泡半径距离的函数的详细计算从未发表过。如果我们想增加裂变气体释放规范与我们目前对裂变气体行为的认识的一致性,对这两个元素的评估是非常有用的。因此,我们建议将解析频率的定义与原子尺度的模拟联系起来。此外,我们提出了从分子动力学计算中获得的累积位移气体量,从中我们得出了一个再溶解剖面,可以用来更好地考虑裂变气体释放代码内的辐照再溶解现象。最重要的是,我们已经建立了一个新的捕获/再溶解模型颗粒内气泡链接到分子动力学模拟,可以很容易地纳入裂变气体释放代码。我们还通过将新模型与参考模型进行比较来检查模型是否正确构建。
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A model for trapping and re-solution regarding intra-granular bubbles in UO2, linked to atomic-scale simulations
In the literature, a clear definition of the irradiation re-solution frequency of gas from bubbles in the UO2 fuel is absent. Moreover, for intra-granular bubbles, a detailed calculation of the cumulated displaced gas quantities in function of the distance from the radius of the bubble after a re-solution event has never been published. The assessment of these two elements is very useful if we want to increase the adherence of fission gas release codes to our present knowledge of the behavior of fission gases. Hence, we suggest to link the definition of the re-solution frequency to atomic-scale simulations. Furthermore, we present the cumulated displaced gas quantities obtained from Molecular Dynamics calculations, from which we have derived a re-solution profile that can be exploited to better consider the irradiation re-solution phenomenon inside Fission Gas Release codes. On top of that, we have built a new trapping/re-solution model for intra-granular bubbles linked to Molecular Dynamics simulations that can be easily incorporated into Fission Gas Release codes. We also check that the model is properly built through the comparison of the new model against a reference.
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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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