二氧化铀中的核能量损失和电子能量损失之间的耦合随辐照温度变化的差异:原位 TEM 研究

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2024-06-04 DOI:10.1016/j.jnucmat.2024.155202
A. Georgesco , G. Gutierrez , J.P. Crocombette , C. Baumier , D. Drouan , C. Onofri
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引用次数: 0

摘要

为了研究二氧化铀中核能量损失与电子能量损失之间的耦合关系,我们在 93 K 的温度下使用 0.39 MeV Xe 和/或 6 MeV Si 离子对薄膜进行了单束或同步双束离子辐照。通过原位透射电子显微镜(TEM)对完美位错环的演变进行了表征。在室温下进行的其他原位透射电子显微镜表征首次揭示了在二氧化钛中存在断层法兰克环,这种环太小,在原位实验和传统的明场运动学成像条件下无法测量。在有利于主要弹道能量损失的单Xe辐照中,我们观察到了小型完美位错环的连续成核,这些环主要通过凝聚效应增长,从而在最后的通量下增大。单硅辐照和双 Xe & 硅辐照都显示出核能损耗和电子能损耗之间的耦合,分别导致环密度显著增加和纠缠线网络的形成。与单Xe辐照相比,这些现象发生在较低的dpa水平,可能是由于硅离子的热尖峰效应造成的。本研究结果与我们之前在 293 K 条件下的研究结果进行了比较,以研究辐照温度对能量损失耦合的作用。与 293 K 相比,在 93 K 的 Xe 辐照下,密度增加,环路变小,这是因为铀间隙迁移被阻止或允许。对于硅辐照,两个温度下的位错演化动力学相似。在此温度范围内,电子激发效应似乎大于辐照温度效应。对于 Xe & Si 辐照,环状动力学变化导致纠结线网络形成的速度更快,因此与 293 K 相比,在 93 K 时环状转变为线状的 dpa 水平更低。
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Differences in coupling between nuclear and electronic energy losses in UO2 with irradiation temperature: An in situ TEM study

To investigate the coupling between nuclear and electronic energy losses in UO2, we irradiated thin foils with 0.39 MeV Xe and/or 6 MeV Si ions at 93 K using single or simultaneous dual beam ion irradiations. The evolution of perfect dislocation loops was characterized by in situ transmission electron microscopy (TEM). Additional ex situ TEM characterizations at room temperature revealed for the first time in UO2 the presence of faulted Frank loops too small to be measured during in situ experiments and conventional bright field kinematical imaging conditions.

For the single Xe irradiation, which favor dominant ballistic energy losses, we observed a continuous nucleation of small perfect dislocation loops, which increase in size for our last fluences by growing through mainly coalescence effect. Both the single Si and dual Xe & Si irradiations showed a coupling between nuclear and electronic energy losses, resulting in a significant loop density increase and a tangled line network formation, respectively. These phenomena occur at lower dpa levels, compared to the single Xe irradiation, likely resulting from the thermal spike effect of Si ions. The present results were compared to our previous work at 293 K to investigate the role of irradiation temperature on the energy losses coupling. For the Xe irradiation, the density increases and the loops are smaller at 93 K compared to 293 K, resulting from the uranium interstitials mobility being prevented or allowed. For the Si irradiation, the dislocation evolution kinetics are similar at both temperatures. The electronic excitations effect seems greater than the irradiation temperature effect in this temperature range. For the Xe & Si irradiation, the loop kinetics change resulting in a tangled line network formation is faster and thus the loop transformation into lines occurs at lower dpa levels at 93 K compared to 293 K. It appears that the irradiation temperature affecting the mobility of some small point defects reduces the electronic excitation effect in this case.

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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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