Molecular dynamic simulations of displacement cascades in molybdenum and molybdenum-rhenium alloys
• Finnis-Sinclair-based Mo-Re potential for MD simulations developed. • In Mo-Re alloys, low thermal conductivity causes larger defect clusters. • Kinetic model basis provided for Mo-Re alloy radiation damage. Molybdenum-Rhenium (Mo-Re) alloys are considered core materials for advanced nuclear reactor components due to their excellent mechanical properties, machinability, and resistance to irradiation damage. However, irradiation-induced embrittlement and phase precipitation at high temperatures, along with transmutation nuclides, have hindered their broader application. To address this, we developed a Mo-Re interatomic potential using the Finnis-Sinclair formalism, facilitating molecular dynamics simulations to study primary irradiation damage. Systemically primary irradiation damage simulations for Mo and Mo-Re alloys have been performed. It’s found that there were more Frenkel-pair defects produced during the stage of thermal spike in Mo-Re alloys but fewer defects survived at the end of the cascade compared to Mo. In addition, the number of large-size interstitial clusters and dislocation loops was higher in Mo-Re alloys than in pure Mo with the same PKA energy. This is mainly attributed to the fact that Mo-Re alloys have lower thermal conductivity, while the binding energies of interstitial clusters and dislocation loops with sizes less than 100 in Mo-Re alloys are comparable to those of pure Mo, resulting in higher defect composites and larger defect sizes in Mo-Re alloys. These findings provide valuable insights into the primary damage mechanisms in Mo-Re alloys under irradiation, offering a foundation for developing kinetic models to simulate radiation-induced microstructural evolution.
Authors
- Peng Jiang (ORCID: https://orcid.org/0000-0002-4291-608X)
- Guangdong Liu (ORCID: https://orcid.org/0009-0008-4801-7844)
- Rongyang Qiu
- Yangchun Chen
- Huiqiu Deng (ORCID: https://orcid.org/0000-0001-8986-104X)
- Xudong Wang (ORCID: https://orcid.org/0000-0002-6575-5127)
- Wen Yang (ORCID: https://orcid.org/0000-0003-1067-2129)
- Hongping Xiang (ORCID: https://orcid.org/0000-0001-7255-5994)
- Xinfu He (ORCID: https://orcid.org/0000-0002-9150-5754)
- Yankun Dou
Institutions
- Hunan University (CN)
- China Institute of Atomic Energy (CN)
Publication Details
- Journal
- Nuclear Materials and Energy
- Published
- 2024-11-04
- DOI
- https://doi.org/10.1016/j.nme.2024.101804
- Citations
- 5
- Primary Topic
- Advanced Materials Characterization Techniques
- Type
- article
- Field-Weighted Citation Impact
- 0.92