Molecular dynamics and machine learning study of tensile behavior in single-crystal tungsten containing He bubbles
• Impact of He bubbles on the tensile behavior of single-crystal tungsten was studied. • The analysis considers varying He bubble sizes, He/V ratios, temperatures, and strain rates. • Machine learning models were used to predict the peak stress. • Provide important insights into tungsten’s tensile deformation under irradiation conditions. Tungsten is commonly used in nuclear fusion plants, where irradiation defects (e.g., He bubbles) are frequently generated. This study investigates the impact of He bubbles on the tensile behavior of single-crystal tungsten through molecular dynamics (MD) simulations. The analysis considers varying He bubble sizes, He/V ratios (the number of helium atoms with respect to the number of vacancies in helium bubble), temperatures, and strain rates. The findings indicate that He bubbles significantly affect the material’s mechanical properties, with larger bubble sizes reducing tensile strength. Dislocation emission initiates from the void surface during tensile deformation. While the He/V ratio slightly influences peak stress values, it does not alter the overall stress–strain curve. Elevated temperatures lower peak stress, whereas higher strain rates increase it. Additionally, machine learning models predict the combined effects of bubble size, He/V ratio, strain rate, and temperature on the peak stress of tungsten, utilizing MD simulation data. This work offers important insights into tungsten’s behavior under irradiation conditions.
Authors
- Pan-dong Lin (ORCID: https://orcid.org/0000-0001-7237-6443)
- Binnian Zhong
- Lin Yan (ORCID: https://orcid.org/0000-0003-3013-8572)
- Shu-gang Cui (ORCID: https://orcid.org/0000-0002-4952-6746)
- Yu‐peng Lu (ORCID: https://orcid.org/0000-0003-0691-3786)
- Hongguang Li (ORCID: https://orcid.org/0000-0002-6579-7300)
- Jun-feng Nie (ORCID: https://orcid.org/0009-0002-6720-3286)
Institutions
- Shandong University (CN)
- Liaocheng University (CN)
- Suzhou Research Institute (CN)
- China National Petroleum Corporation (China) (CN)
- Tsinghua University (CN)
Publication Details
- Journal
- Materials & Design
- Published
- 2025-03-11
- DOI
- https://doi.org/10.1016/j.matdes.2025.113831
- Citations
- 1
- Primary Topic
- Nuclear Materials and Properties
- Type
- article
- Field-Weighted Citation Impact
- 0.52
Funders
- National Natural Science Foundation of China
- Natural Science Foundation of Jiangsu Province
- Ministry of Industry and Information Technology of the People's Republic of China
- Natural Science Foundation of Shandong Province
- China National Nuclear Corporation
- National Key Research and Development Program of China
- National Major Science and Technology Projects of China