Guobao Ma , Gen Li , Zhengxin Tang , Xitao Wang , Jinshan He , Hansheng Bao , Xikou He
{"title":"17-4PH马氏体不锈钢在450℃饱和氧静态铅铋共晶中的腐蚀行为及机理","authors":"Guobao Ma , Gen Li , Zhengxin Tang , Xitao Wang , Jinshan He , Hansheng Bao , Xikou He","doi":"10.1016/j.jnucmat.2025.156155","DOIUrl":null,"url":null,"abstract":"<div><div>17–4PH martensitic stainless steel is used in pressurized water reactors (PWRs) nuclear systems and also shows potential for lead-cooled fast reactors (LFRs), while its resistance to lead-bismuth corrosion is critical. Therefpore, the corrosion behavior of 17–4PH steel in saturated oxygen static lead-bismuth eutectic (LBE) at 450 °C was investigated. It was found that during the initial 3000 h, an incomplete oxide film developed due to the cyclic formation and spalling of oxide layers. By 4500 h, a stable double-layered oxide film was formed, consisting of an outer Fe<sub>3</sub>O<sub>4</sub> layer and an inner FeCr<sub>2</sub>O<sub>4</sub> layer. During internal oxidation, Ni enrichment occurred beneath the internal oxidation layer (IOL)/matrix interface, transforming the body-centered cubic (BCC) martensitic matrix into a face-centered cubic (FCC) Ni-rich phase. The stress induced by the volume change during this phase transition constitutes the predominant driver for premature oxide film spalling. The Ni-rich phases exhibit resistance to oxidation and form isolated islands and flocculent structures within the IOL. Cu accumulates as Cu-rich phases within the IOL and tends to rapidly grow into irregular shapes by adhering to the Ni-rich phase. The flocculent distribution of Cu and Ni within the IOL produced nanoporous regions. These pores acted as diffusion pathways for metallic elements, accelerating oxide film growth after 4500 h. The corrosion mechanism of 17–4PH steel in liquid LBE is discussed based on these observations.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"617 ","pages":"Article 156155"},"PeriodicalIF":3.2000,"publicationDate":"2025-09-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Corrosion behavior and mechanism of 17–4PH martensitic stainless steel in saturated oxygen static lead-bismuth eutectic at 450 °C\",\"authors\":\"Guobao Ma , Gen Li , Zhengxin Tang , Xitao Wang , Jinshan He , Hansheng Bao , Xikou He\",\"doi\":\"10.1016/j.jnucmat.2025.156155\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>17–4PH martensitic stainless steel is used in pressurized water reactors (PWRs) nuclear systems and also shows potential for lead-cooled fast reactors (LFRs), while its resistance to lead-bismuth corrosion is critical. Therefpore, the corrosion behavior of 17–4PH steel in saturated oxygen static lead-bismuth eutectic (LBE) at 450 °C was investigated. It was found that during the initial 3000 h, an incomplete oxide film developed due to the cyclic formation and spalling of oxide layers. By 4500 h, a stable double-layered oxide film was formed, consisting of an outer Fe<sub>3</sub>O<sub>4</sub> layer and an inner FeCr<sub>2</sub>O<sub>4</sub> layer. During internal oxidation, Ni enrichment occurred beneath the internal oxidation layer (IOL)/matrix interface, transforming the body-centered cubic (BCC) martensitic matrix into a face-centered cubic (FCC) Ni-rich phase. The stress induced by the volume change during this phase transition constitutes the predominant driver for premature oxide film spalling. The Ni-rich phases exhibit resistance to oxidation and form isolated islands and flocculent structures within the IOL. Cu accumulates as Cu-rich phases within the IOL and tends to rapidly grow into irregular shapes by adhering to the Ni-rich phase. The flocculent distribution of Cu and Ni within the IOL produced nanoporous regions. These pores acted as diffusion pathways for metallic elements, accelerating oxide film growth after 4500 h. The corrosion mechanism of 17–4PH steel in liquid LBE is discussed based on these observations.</div></div>\",\"PeriodicalId\":373,\"journal\":{\"name\":\"Journal of Nuclear Materials\",\"volume\":\"617 \",\"pages\":\"Article 156155\"},\"PeriodicalIF\":3.2000,\"publicationDate\":\"2025-09-07\",\"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/S0022311525005495\",\"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}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Journal of Nuclear Materials","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0022311525005495","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}
Corrosion behavior and mechanism of 17–4PH martensitic stainless steel in saturated oxygen static lead-bismuth eutectic at 450 °C
17–4PH martensitic stainless steel is used in pressurized water reactors (PWRs) nuclear systems and also shows potential for lead-cooled fast reactors (LFRs), while its resistance to lead-bismuth corrosion is critical. Therefpore, the corrosion behavior of 17–4PH steel in saturated oxygen static lead-bismuth eutectic (LBE) at 450 °C was investigated. It was found that during the initial 3000 h, an incomplete oxide film developed due to the cyclic formation and spalling of oxide layers. By 4500 h, a stable double-layered oxide film was formed, consisting of an outer Fe3O4 layer and an inner FeCr2O4 layer. During internal oxidation, Ni enrichment occurred beneath the internal oxidation layer (IOL)/matrix interface, transforming the body-centered cubic (BCC) martensitic matrix into a face-centered cubic (FCC) Ni-rich phase. The stress induced by the volume change during this phase transition constitutes the predominant driver for premature oxide film spalling. The Ni-rich phases exhibit resistance to oxidation and form isolated islands and flocculent structures within the IOL. Cu accumulates as Cu-rich phases within the IOL and tends to rapidly grow into irregular shapes by adhering to the Ni-rich phase. The flocculent distribution of Cu and Ni within the IOL produced nanoporous regions. These pores acted as diffusion pathways for metallic elements, accelerating oxide film growth after 4500 h. The corrosion mechanism of 17–4PH steel in liquid LBE is discussed based on these observations.
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.