Accelerated failure behavior of Zr702 in boiling nitric acid solutions under constant stress loading

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2024-10-10 DOI:10.1016/j.jnucmat.2024.155453

Yi Liu , Yusheng Zhang , Lianwen Wang , Jinping Wu , Xin Jia , Jianping Xu , Zhonglin Shen , Naizhi Liu , Chengze Liu

引用次数: 0

Abstract

The constant stress tensile deformation behavior of commercial Zr702, used in spent fuel reprocessing industry, was investigated in 108 °C/200 MPa nitric acid solutions and non-corrosive silicone oil. Microscopic characterization of surface as well as cross-section of deformed Zr702 was carried out. In silicone oil, there were minimal cracks observed on the sample's surface. However, a significant number of cracks appeared on the sample's surface in nitric acid solutions. In nitric acid solutions, at the interface between the oxide layer and the matrix, cracks occurred, extended, the oxide film fractured, cracks further expanded, and the stress concentration at the cracks tip led to the formation of new cracks. This cyclic process resulted in the strength of the material decreasing and accelerated failure.

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恒定应力加载下 Zr702 在沸腾硝酸溶液中的加速破坏行为

研究了用于乏燃料后处理工业的商用 Zr702 在 108 °C/200 MPa 硝酸溶液和非腐蚀性硅油中的恒应力拉伸变形行为。对变形 Zr702 的表面和横截面进行了显微表征。在硅油中，样品表面观察到的裂纹极少。但在硝酸溶液中，样品表面出现了大量裂纹。在硝酸溶液中，氧化层和基体之间的界面出现裂纹，裂纹扩展，氧化膜破裂，裂纹进一步扩展，裂纹尖端的应力集中导致新裂纹的形成。这种循环过程导致材料强度下降，加速了材料的失效。

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.