Evolution of dislocation loops and voids in post-irradiation annealed ThO2: A combined in-situ TEM and cluster dynamics investigation

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
Sanjoy Kumar Mazumder , Kaustubh Bawane , J. Matthew Mann , Aaron French , Lin Shao , Lingfeng He , Anter El-Azab
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Abstract

The effect of isochronal annealing on the evolution of dislocation loop and void population in proton irradiated ThO2 has been investigated. Post-irradiation annealing in other actinide oxides like UO2 shows significant loop coarsening. ThO2 samples were irradiated with 2 MeV protons up to a dose of 0.1 dpa at 600 °C. Post-irradiation isochronal annealing was performed at 600, 800, 1000 and 1100 °C for 1 h at each temperature using in-situ TEM. Only faulted 1/3<111> type dislocation loops were observed, and their sizes and distribution were characterized. The population of self-interstitial atom (SIA) dislocation loops did not show any significant growth and coarsening. Additionally, nanometric voids were observed at annealing temperatures of 1000 and 1100 °C. Using cluster dynamics (CD), we have studied the nucleation and growth of point defects and defect clusters, i.e., SIA prismatic dislocation loops and nanometric and sub-nanometric voids in proton irradiated ThO2. The CD model was further utilized to predict the growth and coarsening of loops and voids during isochronal annealing at the experimental and higher temperatures. The model did not predict significant SIA loop growth which closely corresponds to the TEM observations. CD predicted SIA loop coarsening is insignificant even at high annealing temperature of 1500 °C because the model only considers the growth of defect clusters by absorption of like point defects, i.e., SIA loops absorb interstitials and voids absorb vacancies, and cannot account for their migration and coalescence due to elastic interaction. The CD model also predicts the evolution of nanometric voids having mean size within the error bounds of TEM observations.

辐照后退火ThO2中位错环和空洞的演化:原位透射电镜和团簇动力学的结合研究
研究了等时退火对质子辐照ThO2中位错环和空洞居群演化的影响。UO2等其他锕系氧化物辐照后退火表现出明显的环粗化。在600°C下,用2 MeV质子照射到0.1 dpa的剂量。采用原位透射电镜,分别在600、800、1000和1100℃下进行辐照后等时退火1 h。只坏了1/3<111>观察到型位错环,并对其大小和分布进行了表征。自间隙原子(SIA)位错环的居群没有明显的生长和粗化。此外,在1000和1100℃的退火温度下观察到纳米级的空洞。利用团簇动力学(CD)研究了质子辐照的ThO2中点缺陷和缺陷团簇的成核和生长,即SIA棱柱位错环和纳米和亚纳米空洞。利用CD模型进一步预测了在实验温度和高温下等时退火过程中圆环和空洞的生长和粗化。该模型没有预测显著的SIA环路增长,这与TEM观测结果密切相关。即使在1500℃的高退火温度下,CD预测的SIA环粗化也不显著,因为模型只考虑了缺陷团簇的生长,即SIA环吸收间隙和空洞吸收空位,而不能考虑它们由于弹性相互作用而迁移和聚并。CD模型还预测了在TEM观测误差范围内具有平均尺寸的纳米孔隙的演化。
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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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