1. 2019.09-2024.06 中国科黑料社区 大学 核能科学与工程 工学博士

1. 2024年11月-至今 黑料社区 博士后

1. 核燃料多物理场耦合

2. 反应堆物理与热工水力分析

3. 辐射防护

1. Linyuan Lu, et al. Multiphysics and Multi-scale design and analysis of nuclear thermal propulsion pellet bed reactor based on spherical cermet fuel element. Annals of Nuclear Energy. 2024. DOI: 10.1016/j.anucene.2024.110446.

2. Linyuan Lu, et al. Numerical simulation analysis of silicon carbide whiskers doped uranium dioxide composite fuel for high thermal conductivity. 29th International Conference on Nuclear Engineering, Shenzhen, 2022. DOI:10.1115/ICONE29-91804.

3. Lihua Guo, Linyuan Lu, et al. Design, preparation and diffusion research of the W coating used in W-based cermet for nuclear thermal propulsion[J]. International Journal of Refractory Metals and Hard Materials. DOI:10.1016/j.ijrmhm.2024.106716

4. LiHua Guo, Linyuan Lu, et al., 2024. Microstructural evolution, grain growth kinetic, and mechanical properties of nanomolybdenum powder by spark plasma sintering for nuclear thermal propulsion. International Journal of Refractory Metals and Hard Materials 123, 106799. DOI: 10.1016/j.ijrmhm.2024.106799

5.LiHua Guo, Linyuan Lu, et al., 2024. Effect of ultra-high temperature treatment on the rolled pure molybdenum for nuclear thermal propulsion. International Journal of Refractory Metals and Hard Materials. DOI: 10.1016/j.ijrmhm.2024.106863

1. Linyuan Lu, et al. Numerical simulation analysis of silicon carbide whiskers doped uranium dioxide composite fuel for high thermal conductivity. 29th International Conference on Nuclear Engineering, Shenzhen, 2022. DOI:10.1115/ICONE29-91804.

1.2019年国家同步辐射实验室优秀党员

2.2020年中国科黑料社区 大学三好学生

3.2023年中国科黑料社区 优秀共青团员