{"title":"Multi-scale investigation into the irradiation hardening mechanism of reduced activation ferrite/martensitic (RAFM) steels under heavy ion irradiation","authors":"Yong Feng , Hang Xu , Tingping Hou , Xiangheng Xiao , Kaiming Wu","doi":"10.1016/j.fusengdes.2025.115414","DOIUrl":null,"url":null,"abstract":"<div><div>The irradiation resistance of RAFM steels has received considerable attention in the development of candidate structural materials for application in advanced reactors. The present study enhances the mechanical properties and irradiation resistance of RAFM steels by precisely modulating the concent of Si and W. The results show that increasing Si while decreasing W content can make the grain refinement, dislocation line increase, and carbide precipitation of RAFM steel is more fine and diffuse, showing more excellent mechanical properties and lower irradiation hardening rate, and provides a new reference for the design and optimization of RAFM steels. Additionally, the contribution of dislocation loops to irradiation hardening was evaluated using the Dispersive Barrier Hardening (DBH) model, and irradiation-induced matrix atomic misalignment phenomenon and its triggered lattice distortion and dislocation proliferation mechanism were deeply analyzed at the atomic level in conjunction with geometric phase analysis (GPA), and furthermore irradiation-induced segregation of the matrix composition and formation of nano clusters of Si were also revealed by atom probe tomography (APT). These findings have established the nature of irradiation hardening in RAFM steels and may provide a better understanding of irradiation damage mechanisms.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"221 ","pages":"Article 115414"},"PeriodicalIF":2.0000,"publicationDate":"2025-09-02","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/S0920379625006106","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}
引用次数: 0
Abstract
The irradiation resistance of RAFM steels has received considerable attention in the development of candidate structural materials for application in advanced reactors. The present study enhances the mechanical properties and irradiation resistance of RAFM steels by precisely modulating the concent of Si and W. The results show that increasing Si while decreasing W content can make the grain refinement, dislocation line increase, and carbide precipitation of RAFM steel is more fine and diffuse, showing more excellent mechanical properties and lower irradiation hardening rate, and provides a new reference for the design and optimization of RAFM steels. Additionally, the contribution of dislocation loops to irradiation hardening was evaluated using the Dispersive Barrier Hardening (DBH) model, and irradiation-induced matrix atomic misalignment phenomenon and its triggered lattice distortion and dislocation proliferation mechanism were deeply analyzed at the atomic level in conjunction with geometric phase analysis (GPA), and furthermore irradiation-induced segregation of the matrix composition and formation of nano clusters of Si were also revealed by atom probe tomography (APT). These findings have established the nature of irradiation hardening in RAFM steels and may provide a better understanding of irradiation damage mechanisms.
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.