Fracture behavior and grain boundary cohesion of alumina scales formed on ion-irradiated FeCrAl-ODS alloy

IF 3.2 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2025-02-01 DOI:10.1016/j.jnucmat.2025.155663

Hao Yu , Diancheng Geng , Yasuyuki Ogino , Naoko Oono-Hori , Koji Inoue , Sosuke Kondo , Ryuta Kasada , Shigeharu Ukai

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Abstract

The design of FeCrAl ferritic oxide dispersion strengthened (ODS) alloys is based on the formation of a stable alumina scale, which is expected to protect the alloys from extreme heat and corrosion in nuclear applications. To ensure reliable alumina protection in nuclear environment, it is indispensable to concern the radiation tolerance of the alumina scales formed on the FeCrAl ODS alloys. The present study investigates the effect of Fe ions irradiation on fracture modes and grain boundary cohesion of the alumina scales in conjunction with nano-impact tests and micro-double notch shear (DNS) compression tests. Pre-oxidation was carried out in air at 1000 °C to form an α-alumina layer on the surface of Fe-15Cr-7Al-0.5Y₂O₃–0.4Zr (wt.%) ferritic ODS alloy, followed by 6.4 MeV Fe³⁺ ion beam irradiation at 500 °C. Based on the microstructural characterization of the cross-sectional micrographs of nanoindentation imprints on the alumina scales, it was confirmed that the irradiation on the alumina scales resulted in significant intergranular fracture in nanoindentation, whereas the unirradiated alumina scales showed transgranular fracture. The elemental distribution around the alumina grain boundaries was elucidated with the aid of scanning transmission electron microscopy (STEM) and atom probe tomography (APT) observations, and obvious segregation of reactive elements (REs) and intergranular Ti/TiC precipitation were observed after irradiation, indicating the link between the microstructural evolution and the fracture behavior of the alumina scales. The detailed grain boundary cohesion of alumina scales before and after irradiation was accurately measured by the micro-DNS compression tests, and the results showed that the cohesion strength of the alumina decreased significantly after the Fe ions irradiation.

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离子辐照fecr - ods合金上氧化铝鳞片的断裂行为及晶界内聚

铁素体氧化物弥散强化（ODS）合金的设计是基于形成稳定的氧化铝垢，这有望保护合金在核应用中的极端高温和腐蚀。为了保证核环境中氧化铝的可靠防护，必须关注feral ODS合金表面氧化铝鳞片的耐辐射性能。结合纳米冲击试验和微双缺口剪切（DNS）压缩试验，研究了Fe离子辐照对氧化铝鳞片断裂模式和晶界内聚力的影响。在1000℃空气中预氧化Fe-15Cr-7Al-0.5Y2O3-0.4Zr （wt.%）铁素体ODS合金表面形成α-氧化铝层，然后在500℃6.4 MeV Fe3+离子束辐照。通过对氧化铝鳞片上纳米压痕横截面显微形貌的表征，证实了在氧化铝鳞片上辐照导致纳米压痕出现明显的晶间断裂，而未辐照的氧化铝鳞片则表现为穿晶断裂。利用扫描透射电子显微镜（STEM）和原子探针断层扫描（APT）观察了氧化铝晶界周围的元素分布，辐照后观察到明显的活性元素（REs）偏析和晶间Ti/TiC析出，表明氧化铝鳞片的显微组织演化与断裂行为之间存在联系。通过微dns压缩实验，精确测量了辐照前后氧化铝鳞片的详细晶界黏聚力，结果表明，Fe离子辐照后氧化铝鳞片的黏聚力明显降低。

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来源期刊

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.