Jianlong Chai , Dahuan Zhu , Zongxiao Guo , Baoguo Wang , Li Qiao , Rong Yan , Rui Ding , Yang Wang , Peng Wang , Tielong Shen , Zhiguang Wang , Junling Chen
{"title":"Synergistic effects of He, Fe, and deuterium ions on tungsten","authors":"Jianlong Chai , Dahuan Zhu , Zongxiao Guo , Baoguo Wang , Li Qiao , Rong Yan , Rui Ding , Yang Wang , Peng Wang , Tielong Shen , Zhiguang Wang , Junling Chen","doi":"10.1016/j.ijmecsci.2025.110306","DOIUrl":null,"url":null,"abstract":"<div><div>Plasma-facing materials (PFMs) in fusion reactors are subjected to irradiation by high-energy neutrons and high flux plasmas during operation. Especially, in the presence of helium (He), <span><span>irradiation</span><svg><path></path></svg></span> can significantly exacerbate the degradation of material properties. Hence, experimentally investigating the irradiation tolerance of PFMs under the combined effects of He, neutron, and plasma irradiation is essential for ensuring the safe operation of fusion devices. Here, heavy-ion simulations of neutrons were utilized to investigate the synergistic effects of He/Fe/D ions on the microstructural and micromechanical properties of tungsten PFMs. The results show that He + Fe dual-ion irradiation leads to significant irradiation hardening, which is attributed to the increase of both the density and size of dislocation loops. The annealing effect of pre-damaged W under D plasma exposure is considered to be the primary factor driving the evolution of dislocation loops. The significant reduction in the number density of dislocation loops is considered to be the main factor contributing to the reduction in hardening increment after <span>d</span>-ion implantation. To our knowledge, this is among the first studies to simulate the evolution of defects and nanohardness in W PFMs in fusion reactors under the combined influence of He, displacement damage and plasma. This research offers insights into the irradiation damage effects of PFMs in fusion reactors and serves as a reference for the development of new W-based alloy materials.</div></div>","PeriodicalId":56287,"journal":{"name":"International Journal of Mechanical Sciences","volume":"297 ","pages":"Article 110306"},"PeriodicalIF":7.1000,"publicationDate":"2025-04-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"International Journal of Mechanical Sciences","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0020740325003923","RegionNum":1,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"ENGINEERING, MECHANICAL","Score":null,"Total":0}
引用次数: 0
Abstract
Plasma-facing materials (PFMs) in fusion reactors are subjected to irradiation by high-energy neutrons and high flux plasmas during operation. Especially, in the presence of helium (He), irradiation can significantly exacerbate the degradation of material properties. Hence, experimentally investigating the irradiation tolerance of PFMs under the combined effects of He, neutron, and plasma irradiation is essential for ensuring the safe operation of fusion devices. Here, heavy-ion simulations of neutrons were utilized to investigate the synergistic effects of He/Fe/D ions on the microstructural and micromechanical properties of tungsten PFMs. The results show that He + Fe dual-ion irradiation leads to significant irradiation hardening, which is attributed to the increase of both the density and size of dislocation loops. The annealing effect of pre-damaged W under D plasma exposure is considered to be the primary factor driving the evolution of dislocation loops. The significant reduction in the number density of dislocation loops is considered to be the main factor contributing to the reduction in hardening increment after d-ion implantation. To our knowledge, this is among the first studies to simulate the evolution of defects and nanohardness in W PFMs in fusion reactors under the combined influence of He, displacement damage and plasma. This research offers insights into the irradiation damage effects of PFMs in fusion reactors and serves as a reference for the development of new W-based alloy materials.
期刊介绍:
The International Journal of Mechanical Sciences (IJMS) serves as a global platform for the publication and dissemination of original research that contributes to a deeper scientific understanding of the fundamental disciplines within mechanical, civil, and material engineering.
The primary focus of IJMS is to showcase innovative and ground-breaking work that utilizes analytical and computational modeling techniques, such as Finite Element Method (FEM), Boundary Element Method (BEM), and mesh-free methods, among others. These modeling methods are applied to diverse fields including rigid-body mechanics (e.g., dynamics, vibration, stability), structural mechanics, metal forming, advanced materials (e.g., metals, composites, cellular, smart) behavior and applications, impact mechanics, strain localization, and other nonlinear effects (e.g., large deflections, plasticity, fracture).
Additionally, IJMS covers the realms of fluid mechanics (both external and internal flows), tribology, thermodynamics, and materials processing. These subjects collectively form the core of the journal's content.
In summary, IJMS provides a prestigious platform for researchers to present their original contributions, shedding light on analytical and computational modeling methods in various areas of mechanical engineering, as well as exploring the behavior and application of advanced materials, fluid mechanics, thermodynamics, and materials processing.