2020.03-2021.10 德国卡尔斯鲁厄理工学院（KIT）博士

2015.09-2020.03 上海交通大学 核科学与技术 硕博连读

2011.09-2015.06 西安交通大学 核工程与核技术 学士 

2022.06-今          上海交通大学 best365网页版登录官网 助理教授

1.先进核能系统数字孪生

2.热工水力与安全分析

3.不确定性分析

1.核反应堆工程概论（本科生）

2024-2026年，国家自然科学基金青年科学基金项目：基于液体补充机制的近临界压力沸腾危机发生机理研究，主持

2023-2024年，清华大学外协项目：超临界水物性计算模块开发与测试，主持

2023-2026年，上海交通大学双一流建设项目科研启动资金，主持

德国联邦经济和能源部 (BMWi)：Modeling of post-dryout heat transfer and rewetting at fuel rods under BWR and PWR relevant conditions (MOPOW II Project)

德国联邦经济和能源部 (BMWi)：Improvement of the heat transfer modeling in ATHLET for safety analysis of Supercritical Water-Cooled Reactor(VERA Project)

上海市国际科技合作基金：超临界流体流动传热特性研究及模型开发

上海市人工智能创新发展专项：先进小型核能系统精细化建模与智能化数值分析平台建设

1.Song, H.D., Liu, X.J., Song, M.Q., 2023. Comparative study of data-driven and model-driven approaches in prediction of nuclear power plants operating parameters. Applied Energy, 341: 121077.

2. Song, M.Q., Liu, X.J., Cheng, X., 2023. Modelling and experimental validation of heat transfer behavior during trans-critical transients. Annals of Nuclear Energy, 186: 109771.

3.Song, H., Song, M.Q. Liu, X., 2022. Online autonomous calibration of digital twins using machine learning with application to nuclear power plants. Applied Energy, 326: 119995.

4.Song, M.Q., Liu, X.J., Cheng, X., 2022. A new correlation for post-dryout heat transfer in upward vertical flow. Nuclear Engineering and Design, 392: 111747.

5. Song, M.Q., Liu, X.J., Cheng, X., 2021. Prediction of critical heat flux (CHF) for the high-pressure region in uniformly heated vertical round tubes. Annals of Nuclear Energy, 158: 108303. 

6. Song, M.Q., Liu, X.J., 2021. Assessment of CHF and post-CHF Heat Transfer Models for High-Pressure Condition. Frontiers in Energy Research, 9: 782086. 

7. Song, M.Q., Zhang, Q.M., Guo, Y.H., et al., 2016. Numerical modeling of thermal loading of diamond crystal in X-ray FEL oscillators. Chinese Physics C, 40 (4): 048101. 

8. Liu, X.J., Song, M.Q., Cheng, X., 2019. Current status and challenges of supercritical fluid thermal hydraulics. Nuclear Engineering and Design, 354: 110176. 

1.ISSNP-2016：Best Student Papers Award

2.第十六届全国反应堆热工流体学术会议: 优秀论文奖