通过 GISAXS 和 TDS 分析钨中氦气泡的热演化过程

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
Soon Han Bryan Teo , Matt Andrew Trevor Thompson , Nigel Kirby , Danielle Rose Hughes , Nour Hammoud , Aneeqa Khan , Hirohiko Tanaka , Noriyasu Ohno , Paul Mummery , Sarah Louise Harmer , Cormac Seamus Corr
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引用次数: 0

摘要

研究人员利用凝固入射小角 X 射线散射(GISAXS)和热解吸光谱(TDS)来研究钨(W)中氦(He)气泡的热演化。W 样品暴露在低离子能量(20 eV,鞘加速)的 He 等离子体中,样品温度有两种:573 K(低温)和 1050 K(高温)。GISAXS 分析表明,退火至 998 K 后,高温样品的气泡半径中值从 6.42 Å 增加到 12.87 Å。TDS 显示,在等离子体辐照期间,W 中 He 的解吸行为与样品温度有关。高温样品的最大解吸速率比低温样品大一个数量级。高温样品的解吸曲线跨越的温度范围(500 K - 1500 K)比低温样品(500 K - 750 K)更宽。这项工作中观察到的退火行为差异与之前的原位 TEM 退火实验相吻合,并有助于解释等离子体与材料之间的宏观相互作用效应,如再结晶抑制。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Thermal evolution of helium bubbles in tungsten by GISAXS and TDS
Grazing-incidence small-angle x-ray scattering (GISAXS) and thermal desorption spectroscopy (TDS) were used to study the thermal evolution of helium (He) bubbles in tungsten (W). W samples were exposed to a low ion energy (∼20 eV, sheath accelerated) He plasma at two sample temperatures: 573 K (low-temperature) and 1050 K (high-temperature). They were then annealed to temperatures of 773 K, 873 K and 998 K. GISAXS analysis showed an increase in the median bubble radius of the high-temperature samples from 6.42 Å to 12.87 Å as a result of annealing to 998 K. No changes in the bubble radii distributions were observed for the low-temperature samples and the median radius remained at ∼4 Å even after annealing. TDS showed that the desorption behaviour of He in W has a dependence on the sample temperature during plasma irradiation. The higher-temperature sample experienced a maximum desorption rate that is an order of magnitude larger than the low-temperature sample. The desorption profile of the high-temperature sample spanned a wider temperature range, 500 K - 1500 K, than the low-temperature sample, 500 K - 750 K. The formation and thermal evolution of He bubbles in W have a clear dependence on sample temperature during plasma exposure. The differences in annealing behaviour observed in this work agree with prior in-situ TEM annealing experiments and help explain macroscopic plasma-material interaction effects such as recrystallisation suppression.
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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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