Liquid metal embrittlement and fracture behavior of three Mo metals in liquid lead-bismuth eutectic

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

Journal of Nuclear Materials Pub Date : 2024-09-30 DOI:10.1016/j.jnucmat.2024.155434

Yi Zeng , Wanfeng Fu , Xiufu Yu , Jingguo Huang , Xing Gong , Yuanjun Sun , Jing Liu , Xiangdong Ding , Jun Sun

引用次数: 0

Abstract

In this work, liquid metal embrittlement (LME) and the related fracture behavior of Mo, TZM and Mo-14Re were assessed in oxygen-saturated and -depleted LBE at 350°C by means of slow strain rate tensile (SSRT) tests. Neither tensile mechanical property data nor fractographic micrographs show strong evidence of LME. Nevertheless, the observation of deep secondary cracking at the fiber-like grain boundaries of Mo and Mo-14Re tested in LBE suggests occurrence of grain boundary wetting (GBW). Moreover, oxidation-assisted crack initiation and propagation were also identified. Both fracture modes may be a concern when Mo metals with a fiber-like grain structure are used in high-oxygen LBE environment.

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三种钼金属在液态铅铋共晶中的液态金属脆性和断裂行为

在这项工作中，通过慢应变速率拉伸（SSRT）试验，评估了 350°C 下氧饱和和缺氧液态金属脆性（LME）以及 Mo、TZM 和 Mo-14Re 的相关断裂行为。拉伸机械性能数据和断口显微照片都没有显示出 LME 的有力证据。然而，在钼和钼-14Re 的纤维状晶界处观察到的深层二次开裂现象表明，在 LBE 中发生了晶界润湿（GBW）。此外，还发现了氧化辅助裂纹萌发和扩展。在高氧 LBE 环境中使用具有纤维状晶粒结构的钼金属时，这两种断裂模式都可能会引起关注。

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.