Observations of the irradiation hardening behavior in neutron irradiated HT-9 steels through in situ TEM nano-mechanical tests

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

Journal of Nuclear Materials Pub Date : 2024-11-03 DOI:10.1016/j.jnucmat.2024.155497

Tanvi Ajantiwalay , Brandon Bohanon , Patrick H. Warren , Megha Dubey , Yaqiao Wu , Janelle P. Wharry , Assel Aitkaliyeva

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Abstract

Nano-compression and nano-tensile tests were used to investigate the behavior of HT-9 steel neutron irradiated to 4.29 dpa at 469 °C. The deformation of both as-received and neutron irradiated HT-9 was monitored in situ with a transmission electron microscope, which allowed linking microstructure of the material with the evolution of mechanical properties and identifying the mechanisms governing irradiation-induced hardening of these steels. In nano-compression tests, dislocation-mediated deformation is the deformation mechanism in HT-9 steels irradiated at elevated temperatures. In nano-tensile tests, while dislocations contribute to hardening, grain boundaries determine the deformation mechanisms and eventual fracture of HT-9. The paper further examines the size effect for nano-mechanical tests by varying sample dimensions and comparing obtained results to the micro- and bulk-scale mechanical test data.

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通过原位 TEM 纳米力学测试观察中子辐照 HT-9 钢的辐照硬化行为

采用纳米压缩和纳米拉伸试验研究了在 469 °C 下中子辐照 4.29 dpa 的 HT-9 钢的行为。利用透射电子显微镜对原样和中子辐照 HT-9 钢的变形进行了原位监测，从而将材料的微观结构与机械性能的演变联系起来，并确定了这些钢的辐照诱导硬化机制。在纳米压缩试验中，位错介导的变形是 HT-9 钢在高温辐照下的变形机制。在纳米拉伸试验中，虽然位错有助于硬化，但晶界决定了 HT-9 的变形机制和最终断裂。本文通过改变样品尺寸，进一步研究了纳米力学测试的尺寸效应，并将所得结果与微观和大体积力学测试数据进行了比较。

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.