Stress/dynamic straining effects on the corrosion and cracking behavior of a new AFA steel exposed to sCO2

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY
Xianglong Guo , Qiyin Zhou , Zhu Liu , Jianye Chen , Huigang Shi , Lefu Zhang , Gen Zhang , Yongfu Zhao , Yanping Huang
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Abstract

Alumina forming austenitic stainless steel (AFA steel) shows high creep and corrosion resistance in high temperature environments, which makes it a promising candidate structural material for supercritical carbon dioxide (sCO2) Brayton cycle system. The compatibility of AFA steel with sCO2 should be carefully studied as stress corrosion cracking (SCC) poses high threat to the safe operation of the materials. In this work, the SCC of a new AFA steel was evaluated by constant load (CL) testing and slow strain rate tensile (SSRT) testing in 600 °C/20 MPa sCO2 for 185 h. General corrosion (GC) test was also carried out as a comparison. A protective Cr/Al/Si rich oxide layer was formed on the surface of GC specimen, which is also formed on the uncracked area of CL and SSRT tested specimen. The thickness of Cr/Al/Si rich oxide layer firstly increased and then decreased with the increase of nominal strain, which can be attributed to the change of diffusion mechanism from internal-stress controlled mechanism to defects/cracks-controlled mechanism. Intragranular cracking is the only cracking mode of the AFA steel exposed to sCO2, regardless of the testing method, and this result is ascribed to preferentially oxidation of the NiAl precipitates in the AFA steel, which makes it the weak point to be cracked.

Abstract Image

应力/动态应变对新型AFA钢暴露于sCO2下腐蚀和开裂行为的影响
氧化铝奥氏体不锈钢(AFA 钢)在高温环境下具有很强的抗蠕变和抗腐蚀性能,因此有望成为超临界二氧化碳(sCO2)布雷顿循环系统的候选结构材料。由于应力腐蚀开裂(SCC)对材料的安全运行构成很大威胁,因此应仔细研究 AFA 钢与 sCO2 的兼容性。在这项工作中,通过在 600 °C/20 MPa sCO2 中持续 185 h 的恒定载荷 (CL) 测试和慢应变速率拉伸 (SSRT) 测试,对新型 AFA 钢的 SCC 进行了评估。GC 试样表面形成了富含 Cr/Al/Si 的氧化物保护层,CL 和 SSRT 测试试样的未开裂区域也形成了这种保护层。随着标称应变的增加,富含铬/铝/硅的氧化层厚度先增大后减小,这可能是由于扩散机制从内应力控制机制转变为缺陷/裂纹控制机制。无论采用哪种测试方法,晶间开裂都是暴露于 sCO2 的 AFA 钢的唯一开裂模式,这一结果归因于 AFA 钢中的 NiAl 沉淀优先氧化,使其成为开裂的薄弱点。
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来源期刊
Journal of Nuclear Materials
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.
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