{"title":"Stress-induced corrosion behavior of martensitic P91 steel in high-temperature and high-pressure supercritical carbon dioxide for brayton cycle system","authors":"Shengxu Wang, Yingying Yang, Qiguo Yang, Aizheng Li, Yan Ren, Weidong Wu","doi":"10.1016/j.jnucmat.2025.155939","DOIUrl":null,"url":null,"abstract":"<div><div>The corrosion behavior of alloy materials employed in high-temperature components of supercritical carbon dioxide (S-CO<sub>2</sub>) Brayton cycle power generation systems is a critical factor influencing both the efficiency and service life of the system. In this study, we investigated the corrosion behavior of martensitic P91 steel exposed to S-CO<sub>2</sub> at 550 °C and 20 MPa for up to 1000 h. The effect of stress loading (0/210/420 MPa) on the corrosion behavior was studied using a four-point bending stress loading device. The results revealed that the surface of the specimen exhibited extensive corrosion areas, indicating that the corrosion type of martensitic P91 was uniform corrosion rather than localized corrosion. In addition, the corrosion layer on the surface displayed a carbon deposition phenomenon, which differs from the metal corrosion typically observed in conventional steam cycles. The thickness of the corrosion product layer on the specimen surface under three conditions were 15.6 μm, 17.6 μm, and 27 μm, respectively. All corrosion layers exhibited a double-layer structure, with the outer layer primarily composed of Fe<sub>3</sub>O<sub>4</sub> and the inner layer mainly consisting of FeCr<sub>2</sub>O<sub>4</sub> and Fe<sub>2</sub>SiO<sub>4</sub>. This indicates that stress loading has minimal impact on the phase composition of the corrosion products, but it accelerates the corrosion rate of the steel, increasing the thickness of the oxide layer. Additionally, the oxide layer thickness increases with rising stress values, accompanied by localized spalling.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"615 ","pages":"Article 155939"},"PeriodicalIF":3.2000,"publicationDate":"2025-05-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Journal of Nuclear Materials","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0022311525003332","RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q3","JCRName":"MATERIALS SCIENCE, MULTIDISCIPLINARY","Score":null,"Total":0}
引用次数: 0
Abstract
The corrosion behavior of alloy materials employed in high-temperature components of supercritical carbon dioxide (S-CO2) Brayton cycle power generation systems is a critical factor influencing both the efficiency and service life of the system. In this study, we investigated the corrosion behavior of martensitic P91 steel exposed to S-CO2 at 550 °C and 20 MPa for up to 1000 h. The effect of stress loading (0/210/420 MPa) on the corrosion behavior was studied using a four-point bending stress loading device. The results revealed that the surface of the specimen exhibited extensive corrosion areas, indicating that the corrosion type of martensitic P91 was uniform corrosion rather than localized corrosion. In addition, the corrosion layer on the surface displayed a carbon deposition phenomenon, which differs from the metal corrosion typically observed in conventional steam cycles. The thickness of the corrosion product layer on the specimen surface under three conditions were 15.6 μm, 17.6 μm, and 27 μm, respectively. All corrosion layers exhibited a double-layer structure, with the outer layer primarily composed of Fe3O4 and the inner layer mainly consisting of FeCr2O4 and Fe2SiO4. This indicates that stress loading has minimal impact on the phase composition of the corrosion products, but it accelerates the corrosion rate of the steel, increasing the thickness of the oxide layer. Additionally, the oxide layer thickness increases with rising stress values, accompanied by localized spalling.
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.