不同Ti和V含量的feral - y2o3 ODS钢的显微组织和物相研究

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
Jaroslaw J. Jasinski , Tomasz Stasiak , Wojciech Chmurzynski , Lukasz Kurpaska , Marcin Chmielewski , Malgorzata Frelek-Kozak , Magdalena Wilczopolska , Katarzyna Mulewska , Maciej Zielinski , Marcin Kowal , Ryszard Diduszko , Witold Chrominski , Jacek Jagielski
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引用次数: 0

摘要

铁铁基钢被认为是有前途的高温核应用材料。在过去的几年里,人们研究了各种成分来评估它们的机械性能、结构完整性和抗辐射损伤性。然而,与纯FeCrAl合金相比,对添加不同合金元素的FeCrAl- ods钢的显微组织和相组成的研究较少。本文提出了一种新的研究途径,即开发添加Y2O3、Ti和V的FeCrAl基ODS钢。在行星球磨机中,在氩气环境下,用氧化钇对纯金属组分进行机械合金化。两种样品中均添加1.0 wt.%的钛,其中一种样品中添加0.5 wt.%的钒,以验证其对结构稳定性和硬度的影响。采用火花等离子烧结(SPS)技术对粉末进行固结。随后,采用SEM-EDS、EBSD、TEM-EDS、XRD、XRF、纳米压痕和维氏显微硬度等方法对材料的微观结构、化学成分、相组成和硬度进行了测定。实验数据表明,机械合金化后的粉末较为均匀,而SPS后的块状样品较为致密。显微组织观察表明,bcc基体的晶界和晶粒内部存在氧化颗粒和碳化物,表明其抗辐射损伤能力增强。在ODS钢基体中加入纳米级氧化物颗粒(15 ~ 50 nm),可以通过影响铬在ODS钢基体中的扩散路径,显著降低高温时效脆化的影响。钒的加入使样品的硬度从3.78±0.34 GPa提高到4.83±0.43 GPa。所提出的实验结果在研究和开发适合在第四代裂变反应堆和聚变反应堆恶劣条件下运行的铁基和铝基ODS材料方面是有希望的。
本文章由计算机程序翻译,如有差异,请以英文原文为准。

Microstructure and phase investigation of FeCrAl-Y2O3 ODS steels with different Ti and V contents

Microstructure and phase investigation of FeCrAl-Y2O3 ODS steels with different Ti and V contents

FeCrAl-based steels are considered promising materials for high-temperature nuclear applications. Over the past years, various compositions have been studied to assess their mechanical properties, structural integrity, and radiation damage resistance. However, the microstructure and phase composition of FeCrAl-ODS steels with the addition of different alloying elements are less commonly studied than pure FeCrAl alloys. The paper presents a novel research path for developing FeCrAl matrix ODS steels with Y2O3, Ti, and V additions. The materials synthesis consisted of mechanical alloying of pure metallic components with yttrium oxide in a planetary ball mill under an argon atmosphere. Titanium was added in the amount of 1.0 wt.% to both samples, while 0.5 wt.% of vanadium was added to one sample to verify its impact on the structural stability and hardness. The spark plasma sintering (SPS) technique was used to consolidate the powders. Afterward, the microstructure, chemical composition, phase composition, and hardness were assessed using SEM-EDS, EBSD, TEM-EDS, XRD, XRF, Nanoindentation, and Vickers microhardness. The experimental data reveal rather homogeneous powders after mechanical alloying and dense bulk samples after SPS. The microstructure observations show oxide particles and carbides on the grain boundaries and inside grains of the bcc matrix, which suggests elevated radiation damage resistance. The presence of nanoscale oxide particles (15–50 nm) in the matrix could significantly reduce the impact of aging embrittlement at high temperatures by affecting the chromium diffusion pathways in the ODS steel matrix. The addition of vanadium leads to an improvement of hardness to 4.83±0.43 GPa compared to 3.78±0.34 GPa for the sample without vanadium. Presented experimental results are promising in terms of research and development of FeCr and Al-based ODS materials tailored to operate under harsh conditions in generation IV fission reactors and fusion reactors.

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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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