Investigation of radiation-induced segregation at fully characterized coherent twin boundaries in proton-irradiated 316L stainless steel

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2024-10-28 DOI:10.1016/j.jnucmat.2024.155470

Sara K. Wonner, Pascal Bellon

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Abstract

The effect of grain boundary character on radiation-induced segregation (RIS) is investigated in a 316L austenitic stainless steel irradiated with 2 MeV protons at 360 °C. Orientation imaging microscopy is employed to select specific grain boundaries (GBs), including Σ3{111} coherent twin boundaries, fully characterized by a five-degree of freedom analysis, as well as high angle GBs. Chemical maps along these GBs below the irradiated surface, at depths corresponding to damage levels ranging from 2.3 dpa to 4.2 dpa, are acquired using energy-dispersive spectrometry in a scanning transmission electron microscope (STEM-EDS). RIS levels are defined as elemental GB excess quantities and are used to compare RIS at twin boundaries and high-angle GBs. These measurements are complemented by the analysis of void distributions near GBs and by characterizing the structure of coherent twin GBs prior to and after irradiation using high-resolution STEM imaging. In light of the results obtained in this work, the evolution of the efficiency for point defect elimination of coherent twin GBs with the irradiation dose is discussed.

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质子辐照 316L 不锈钢中完全表征相干孪晶边界的辐射诱导偏析研究

在 360 °C、2 MeV 质子辐照的 316L 奥氏体不锈钢中，研究了晶界特征对辐射诱发偏析（RIS）的影响。采用方位成像显微镜选择特定的晶界（GB），包括通过五自由度分析充分表征的Σ3{111}相干孪晶晶界以及高角度晶界。在扫描透射电子显微镜（STEM-EDS）中使用能量色散光谱法获取了辐照表面以下这些 GB 的化学图谱，其深度与 2.3 dpa 至 4.2 dpa 的损伤水平相对应。RIS 水平被定义为元素 GB 过剩量，用于比较孪晶边界和高角度 GB 的 RIS。通过分析 GB 附近的空隙分布，以及利用高分辨率 STEM 成像分析辐照前后相干孪生 GB 的结构，对这些测量结果进行了补充。根据这项工作获得的结果，讨论了相干孪晶 GB 的点缺陷消除效率随辐照剂量的变化。

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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.