Liquid lead resistance and cracking of novel 1Al-Sc-Y ODS Eurofer steel

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

Journal of Nuclear Materials Pub Date : 2024-08-20 DOI:10.1016/j.jnucmat.2024.155306

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引用次数: 0

Abstract

Novel 1Al-Sc-Y ODS Eurofer steel for use in high temperature heavy metal cooling technologies has been developed by a mechanical alloying of feedstock powders using spark plasma sintering technique and a two-step heat treatment. The 1 wt.% Al has been added to increase the resistance in the environments at high temperatures. This paper reports the microstructure and mechanical properties of the material in the as-manufactured state, and after exposure in liquid lead. Emphasis is placed on the determination of environmental resistance and namely susceptibility to cracking in contact with liquid lead. The material specimens were exposed to static liquid lead with an average concentration of oxygen 1 × 10⁻⁶ wt.% at 600 °C for 1000 h and then, tensile, impact, fracture toughness and slow three-point bend testing was performed. After the exposure, some Pb penetrated into a subsurface layer which in fact caused wetting but testing with the remains of liquid lead at the surface of corroded specimens at 350 °C showed that the steel stayed very low susceptible to the cracking.

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新型 1Al-Sc-Y ODS Eurofer 钢的抗液铅性能和开裂性能

通过使用火花等离子烧结技术对原料粉末进行机械合金化处理和两步热处理，开发出了用于高温重金属冷却技术的新型 1Al-Sc-Y ODS Eurofer 钢。其中添加的 1 wt.% Al 可提高在高温环境中的耐受性。本文报告了材料在制造状态和暴露于液态铅后的微观结构和机械性能。重点是确定材料的耐环境性，以及与液态铅接触后的开裂敏感性。将材料试样暴露于平均氧浓度为 1 × 10-6 wt.%、温度为 600 °C 的静态液态铅中 1000 小时，然后进行拉伸、冲击、断裂韧性和慢速三点弯曲测试。暴露后，一些铅渗入表层下，事实上造成了润湿，但在 350 °C 下用腐蚀试样表面的液态铅残留物进行的测试表明，钢的开裂易感性非常低。

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.