K. Mulewska , D. Kalita , M. Wilczopolska , W. Chromiński , P.A. Ferreirós , Ł. Kurpaska
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Transmission electron microscopy (TEM) analysis revealed that irradiation at RT leads to a dense distribution of dislocation loops, which act as strong obstacles to dislocation glide, significantly increasing the critical stress required for plastic deformation. In contrast, irradiation at 300 °C results in a lower density of defects in the matrix, with dislocation loops observed near pre-existing dislocation lines. This defect configuration facilitates the formation of dislocation channels, reducing overall obstruction to dislocation motion and leading to a decrease in pop-in stress compared to RT-irradiated samples. However, despite the apparent increase in dislocation mobility, Cr-decorated dislocation loops in the 300 °C-irradiated sample act as pinning sites, impeding the contribution of pre-existing dislocations to plastic deformation and necessitating the nucleation of new dislocations. 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引用次数: 0
摘要
了解铁铬合金在辐照下的力学行为对其在核环境中的应用至关重要。本研究研究了五种不同条件下Fe- 9cr合金位错结构的演变及其对纳米压痕响应的影响:(1)未辐照的原始材料,(2)未辐照的300℃退火材料,(3)10 MeV Fe 2 +离子在室温下照射到5 dpa, (4) 10 MeV Fe 2 +离子在300℃照射到1 dpa, (5) 10 MeV Fe 2 +离子在300℃照射到5 dpa。透射电镜(TEM)分析表明,在RT处辐照导致位错环密集分布,这是位错滑动的强大障碍,显著增加了塑性变形所需的临界应力。相比之下,300°C的辐照导致基体中缺陷密度较低,在先前的位错线附近观察到位错环。这种缺陷结构有利于位错通道的形成,减少了对位错运动的总体阻碍,导致与rt辐照样品相比,弹出应力降低。然而,尽管位错迁移率明显增加,但在300°c辐照的样品中,cr修饰的位错环充当了钉住位点,阻碍了先前的位错对塑性变形的贡献,并需要新位错的成核。记录的力学性能,连同微观结构的演变,为Fe-Cr合金的力学响应提供了重要的见解,为其在核应用中的性能提供了有价值的启示。
Microstructural evolution and mechanical response of ion-irradiated Fe-9Cr alloys: Insights from nanoindentation
Understanding the mechanical behavior of Fe-Cr alloys under irradiation is crucial for their application in nuclear environments. This study investigates the evolution of dislocation structures and their impact on the nanoindentation response of Fe-9Cr alloys in five distinct conditions: (1) non-irradiated pristine material, (2) non-irradiated material annealed at 300 °C, (3) material irradiated with 10 MeV Fe²⁺ ions to 5 dpa at room temperature, (4) material irradiated with 10 MeV Fe²⁺ ions to 1 dpa at 300 °C, and (5) material irradiated with 10 MeV Fe²⁺ ions to 5 dpa at 300 °C. Transmission electron microscopy (TEM) analysis revealed that irradiation at RT leads to a dense distribution of dislocation loops, which act as strong obstacles to dislocation glide, significantly increasing the critical stress required for plastic deformation. In contrast, irradiation at 300 °C results in a lower density of defects in the matrix, with dislocation loops observed near pre-existing dislocation lines. This defect configuration facilitates the formation of dislocation channels, reducing overall obstruction to dislocation motion and leading to a decrease in pop-in stress compared to RT-irradiated samples. However, despite the apparent increase in dislocation mobility, Cr-decorated dislocation loops in the 300 °C-irradiated sample act as pinning sites, impeding the contribution of pre-existing dislocations to plastic deformation and necessitating the nucleation of new dislocations. Recorded mechanical properties, together with microstructural evolution, provide critical insights into the mechanical response of Fe-Cr alloys, offering valuable implications for their performance in nuclear applications.
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.