MX precipitate behavior in an irradiated advanced Fe-9Cr steel: Helium sequestration and cavity swelling performance

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2025-03-07 DOI:10.1016/j.jnucmat.2025.155727

T.M. Kelsy Green , Tim Graening , Weicheng Zhong , Ying Yang , Kevin G. Field

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Abstract

This work is the third and final part in an initial series on addressing the behavior of MX precipitate stability in an advanced Fe-9Cr reduced activation ferritic/martensitic (RAFM) alloy under fusion-relevant ion irradiation conditions. Here, the helium trapping properties of MX precipitates are investigated across varying damage levels (15–100 dpa), temperatures (400–600 °C), and helium doses (10–25 appm He/dpa) using sophisticated dual ion beam experiments and electron microscopy. Results indicate that individual MX precipitates efficiently sequester helium in the form of nanoscale bubbles at the precipitate-matrix interfaces near the peak swelling temperature (∼5 bubbles/precipitate at 500 °C). Swelling was primarily due to matrix cavities. The Fe-9Cr alloy reached 2% swelling by 100 dpa, suggesting a shift to steady-state swelling around 50 dpa at 500 °C. However, MX precipitate dissolution beginning at 15 dpa did not coincide with this onset of steady-state swelling.

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辐照高级Fe-9Cr钢中MX析出行为：氦封存和空腔膨胀性能

本研究是研究高级Fe-9Cr低活化铁素体/马氏体（RAFM）合金在熔合相关离子辐照条件下MX沉淀稳定性行为系列的第三部分，也是最后一部分。在这里，使用复杂的双离子束实验和电子显微镜研究了不同损伤水平（15-100 dpa）、温度（400-600°C）和氦剂量（10-25 appm He/dpa）下MX沉淀的氦捕获特性。结果表明，在峰值膨胀温度附近（500℃时约5个气泡/沉淀），单个MX沉淀有效地以纳米级气泡的形式在沉淀-基体界面隔离氦。肿胀主要是由于基质空腔。Fe-9Cr合金在100 dpa时膨胀率达到2%，表明在500℃时膨胀率在50 dpa左右转变为稳态膨胀。然而，从15dpa开始的MX沉淀溶解并没有与稳态膨胀的开始一致。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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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.