Helium behavior in W-Ta-Cr-V high-entropy alloy: An interatomic potential and molecular dynamics simulations

IF 2.8 2区 工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2025-03-04 DOI:10.1016/j.jnucmat.2025.155728
Suming Chen , Yangchun Chen , Rongjian Pan , Xichuan Liao , Rongyang Qiu , Long Guo , Zhixiao Liu , Huiqiu Deng
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Abstract

Tungsten-based high-entropy alloys have demonstrated promising performance as materials for nuclear fusion. Understanding typical helium behavior in these alloys is crucial for assessing their resistance to helium ion irradiation and underlying mechanisms. In this study, we developed a W-Ta-Cr-V-He five-element interatomic potential and used it to examine helium behavior in the W38Ta36Cr15V11 alloy through molecular dynamics simulations. Our results reveal several notable differences between W38Ta36Cr15V11 and pure tungsten. Specifically, the formation and binding energies of helium clusters and helium-vacancy clusters in W38Ta36Cr15V11 are significantly lower than in pure tungsten, indicating reduced binding ability for helium atoms and a weaker self-trapping effect. Furthermore, the alloy exhibits a significantly higher diffusion energy barrier for a single interstitial helium atom, resulting in decreased helium mobility and further reducing the tendency for helium cluster formation. The study also highlights distinct mechanisms of helium bubble growth: in W38Ta36Cr15V11, helium clusters lead to the expulsion of interstitial atoms without forming dislocation loops, whereas in pure tungsten, dislocation loop emission accompanies helium bubble growth. Temperature-dependent simulations show that helium bubble nucleation is notably suppressed in W38Ta36Cr15V11 compared to pure tungsten, with weaker clustering of helium atoms observed at various temperatures. The developed W-Ta-Cr-V-He potential and the resulting data offer valuable insights into helium behavior in tungsten-based high-entropy alloys.
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来源期刊
Journal of Nuclear Materials
Journal of Nuclear Materials 工程技术-材料科学:综合
CiteScore
5.70
自引率
25.80%
发文量
601
审稿时长
63 days
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.
期刊最新文献
Identifying He- and H-vacancy complexes in 3C-SiC by temperature-dependent positron annihilation lifetime calculations Helium behavior in W-Ta-Cr-V high-entropy alloy: An interatomic potential and molecular dynamics simulations Editorial Board Modeling and analysis for the anisotropic irradiation swelling of porous SiC/SiC composites Microstructural evolution of neutron irradiated ultrafine-grained austenitic stainless steel
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