博士后
师资队伍

卢林远

  • 博士后
  • 电话:64355111-6592
  • 邮箱:lulinyuan_195342@sjtu.edu.cn
  • 办公地点:东部教学楼309

学术经历

1. 2019.09-2024.06 中国科学院大学 核能科学与工程 工学博士

工作经历

1. 2024年11月-至今 上海交通大学国家电投智慧能源创新学院 博士后

研究方向

1. 核燃料多物理场耦合

2. 反应堆物理与热工水力分析

科研项目

1. 2024.06-2026.06  中国核工业集团公司领创研究项目和松山湖材料实验室开放研究基金(2023SLABFN09),参与。

代表性论文

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. Linyuan Lu, et al. Design research of spherical cermet fuel element for nuclear thermal propulsion based on multi-physics coupling method. Nuclear Engineering and Design. 2025. DOI: 10.1016/j.nucengdes.2025.114334.

4. Effective thermal conductivity evaluation of SPS-nanoscale W powder sintered at different temperature by microstructural-simulation-based Machine Learning. Materials Today Communication. DOI: 10.1016/j.mtcomm.2025.113451(通讯).

5. Investigation of the influence and mechanism of annealing temperature on the crushing strength of W layer prepared by chemical vapor deposition for nuclear thermal propulsion: Experimental and modeling analysis. DOI: 10.1016/j.ijrmhm.2025.1072(通讯).

国际会议

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.

荣誉奖励

1.2019年国家同步辐射实验室优秀党员

2.2020年中国科学院大学三好学生

3.2023年中国科学院优秀共青团员