Xianglong Guo , Qiyin Zhou , Zhu Liu , Jianye Chen , Huigang Shi , Lefu Zhang , Gen Zhang , Yongfu Zhao , Yanping Huang
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引用次数: 0
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.
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.