Characterization of irradiation-induced dislocation loops in Vanadium at 25-500 °C

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
Q. Zhang , L. Li , S. Chen , Y. Dong , E. Fu , X. Chang , L. Bao , X. Guo , K. Jin , Y. Xue
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Abstract

Vanadium-based alloys have emerged as promising candidates for structural materials in fusion applications. However, as its base metal, the response of V to irradiation has received limited attention in prior studies. To gain a fundamental understanding of the irradiation damage in V, its microstructure evolution under 6 MeV Ti ion irradiation at 25–500 °C is investigated in the present study, with the focus on the detailed and comprehensive characterization of the behavior of the irradiation-introduced dislocation loops. Under room temperature irradiation, the “black dot” dislocation loops agglomerate linearly into rafts, during which their Burgers vectors are well aligned. With the temperature increases to 300 °C, the size of rafts increases and the density decreases, while the size of small loops maintains similar to the room temperature irradiation condition. As the irradiation temperature reaches 500 °C, the defects become highly mobile, resulting in the formation of extended dislocation loops or lines with hundreds of nanometers in size, with the rafts vanishing. All the observable loops under this irradiation temperature range exhibit the Burgers vectors of a/2 < 111>. All the loops observed in the displacement region are identified to be interstitial-type, while a small portion of loops observed in the diffusion region under elevated temperatures are vacancy-type.
25-500 ℃辐照诱导的钒中位错环的表征
钒基合金已成为核聚变应用中很有前途的候选结构材料。然而,作为其基本金属,钒对辐照的响应在之前的研究中受到的关注有限。为了从根本上了解 V 的辐照损伤,本研究调查了其在 25-500 ℃ 的 6 MeV Ti 离子辐照下的微观结构演变,重点是对辐照引入的位错环的行为进行详细而全面的表征。在室温辐照下,"黑点 "位错环线性聚集成筏状,其布格斯矢量排列整齐。随着温度升高到 300 ℃,筏的尺寸增大,密度减小,而小环圈的尺寸保持与室温辐照条件下相似。当辐照温度达到 500 ℃ 时,缺陷变得高度流动,从而形成数百纳米大小的扩展位错环或线,筏消失。在此辐照温度范围内,所有可观察到的环都呈现出 a/2 <111>的伯格斯矢量。在位移区观察到的所有环路都被确定为间隙型环路,而在高温下的扩散区观察到的一小部分环路则为空位型环路。
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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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