{"title":"应力加载条件下316L奥氏体钢在液态锂铅合金中的腐蚀行为","authors":"Masatoshi Kondo , Yota Koike , Kenshi Ohno , Kaoru Omiya , Minho Oh , Naoko Oono-Hori","doi":"10.1016/j.fusengdes.2025.115115","DOIUrl":null,"url":null,"abstract":"<div><div>The material compatibility is one of the important issues for the development of liquid LiPb blanket of fusion reactors. The corrosion characteristics of 316L austenitic steel under tensile stress loadings were investigated by means of the immersion of C-ring specimens into liquid LiPb at 573 K and 773 K for 1000 h. The corrosion of 316L austenitic steel was negligibly small in liquid LiPb at 573 K regardless of the tensile stress loadings. The corrosion was caused by the dissolution of alloying elements (i.e., Fe, Cr and Ni) on the surface of specimens exposed to liquid LiPb at 773 K without the tensile stress loadings. The phase transformation from fcc structure of austenite to bcc structure of ferrite was induced on the surface according to the depletion of Ni in the corrosion procedure, which was austenite-stabilizing element. The dissolution corrosion was mitigated on the area around the apex of the C-ring specimens where the tensile stresses of 100 MPa and 200 MPa were applied. Cr- and C- rich regions were detected on the tensile-strained area of the specimens which could function as an anti-corrosion layer in liquid LiPb. The enrichment of Cr was induced by the depletion of Fe and Ni on the surface since the solubility of Cr was smaller than that of Fe and Ni in liquid LiPb. The dissolution of Cr could be mitigated by the carburization on the surface. The stress-induced martensitic transformation and the introduction of dislocations could contribute the formation of Cr- and C- rich regions.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"216 ","pages":"Article 115115"},"PeriodicalIF":1.9000,"publicationDate":"2025-04-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Corrosion behavior of 316L austenitic steel in liquid lithium lead alloy under stress loading conditions\",\"authors\":\"Masatoshi Kondo , Yota Koike , Kenshi Ohno , Kaoru Omiya , Minho Oh , Naoko Oono-Hori\",\"doi\":\"10.1016/j.fusengdes.2025.115115\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>The material compatibility is one of the important issues for the development of liquid LiPb blanket of fusion reactors. The corrosion characteristics of 316L austenitic steel under tensile stress loadings were investigated by means of the immersion of C-ring specimens into liquid LiPb at 573 K and 773 K for 1000 h. The corrosion of 316L austenitic steel was negligibly small in liquid LiPb at 573 K regardless of the tensile stress loadings. The corrosion was caused by the dissolution of alloying elements (i.e., Fe, Cr and Ni) on the surface of specimens exposed to liquid LiPb at 773 K without the tensile stress loadings. The phase transformation from fcc structure of austenite to bcc structure of ferrite was induced on the surface according to the depletion of Ni in the corrosion procedure, which was austenite-stabilizing element. The dissolution corrosion was mitigated on the area around the apex of the C-ring specimens where the tensile stresses of 100 MPa and 200 MPa were applied. Cr- and C- rich regions were detected on the tensile-strained area of the specimens which could function as an anti-corrosion layer in liquid LiPb. The enrichment of Cr was induced by the depletion of Fe and Ni on the surface since the solubility of Cr was smaller than that of Fe and Ni in liquid LiPb. The dissolution of Cr could be mitigated by the carburization on the surface. The stress-induced martensitic transformation and the introduction of dislocations could contribute the formation of Cr- and C- rich regions.</div></div>\",\"PeriodicalId\":55133,\"journal\":{\"name\":\"Fusion Engineering and Design\",\"volume\":\"216 \",\"pages\":\"Article 115115\"},\"PeriodicalIF\":1.9000,\"publicationDate\":\"2025-04-24\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Fusion Engineering and Design\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S0920379625003126\",\"RegionNum\":3,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q1\",\"JCRName\":\"NUCLEAR SCIENCE & TECHNOLOGY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Fusion Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0920379625003126","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
Corrosion behavior of 316L austenitic steel in liquid lithium lead alloy under stress loading conditions
The material compatibility is one of the important issues for the development of liquid LiPb blanket of fusion reactors. The corrosion characteristics of 316L austenitic steel under tensile stress loadings were investigated by means of the immersion of C-ring specimens into liquid LiPb at 573 K and 773 K for 1000 h. The corrosion of 316L austenitic steel was negligibly small in liquid LiPb at 573 K regardless of the tensile stress loadings. The corrosion was caused by the dissolution of alloying elements (i.e., Fe, Cr and Ni) on the surface of specimens exposed to liquid LiPb at 773 K without the tensile stress loadings. The phase transformation from fcc structure of austenite to bcc structure of ferrite was induced on the surface according to the depletion of Ni in the corrosion procedure, which was austenite-stabilizing element. The dissolution corrosion was mitigated on the area around the apex of the C-ring specimens where the tensile stresses of 100 MPa and 200 MPa were applied. Cr- and C- rich regions were detected on the tensile-strained area of the specimens which could function as an anti-corrosion layer in liquid LiPb. The enrichment of Cr was induced by the depletion of Fe and Ni on the surface since the solubility of Cr was smaller than that of Fe and Ni in liquid LiPb. The dissolution of Cr could be mitigated by the carburization on the surface. The stress-induced martensitic transformation and the introduction of dislocations could contribute the formation of Cr- and C- rich regions.
期刊介绍:
The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.