2011.09-2015.06，上海交通大学，核工程与核技术专业，获学士学位。
2015.09-2021.03，上海交通大学，核科学与技术专业，获博士学位。

2021.06至今，上海交通大学，核科学与工程学院，助理研究员

反应堆热工水力，两相流动与传热，先进燃料组件

1. 科技部重大专项，“反应堆水力特性试验用高稳定性模拟燃料组件的制造和标定”。主要研究人员。
2. 科技部重大专项，“自主化定型组件流量平衡试验”。主要研究人员。
3. 科技部重大专项，“自主化定型组件压降试验”。主要研究人员。
4. 中广核研究院，“燃料组件CHF合作试验”。主要研究人员。

[1] Chen S, Gu H, Liu M, et al. Experimental investigation on heat transfer to supercritical water in a three-rod bundle with spacer grids[J]. Applied Thermal Engineering, 2020, 164: 114466.
[2] Chen S, Gu H. CFD simulation and analysis of reactor integral hydraulic tests[J]. Annals of Nuclear Energy, 2020, 135: 106962.
[3] Chen S, Liu D, Xiao Y, et al. Experimental study on onset of nucleate boiling and flow boiling heat transfer in a 5×5 rod bundle at low flow rate[J]. International Journal of Heat and Mass Transfer, 2019, 137: 727-739.
[4] Chen S, Liu D, Liu M, et al. Numerical simulation and analysis of flow and heat transfer in a 5×5 vertical rod bundle with buoyancy effects[J]. Applied Thermal Engineering, 2019, 163: 114221.
[5] Chen S, Xiao Y, Gu H. Experimental study on boiling heat transfer in a three-rod bundle at near-critical pressure[J]. Annals of Nuclear Energy, 2019, 131: 196-209.
[6] Chen S, Hu Z, Xiao Y, et al. Experimental investigation of subcooled flow boiling heat transfer in helical coils[J]. Nuclear Engineering and Design, 2018, 327: 187-197.
[7] Xiao Y, Hu Z, Chen S, et al. Experimental study on dryout characteristics of steam-water flow in vertical helical coils with small coil diameters[J]. Nuclear Engineering and Design, 2018, 335: 303-313.
[8] Xiao Y, Hu Z, Chen S, et al. Experimental investigation of boiling heat transfer in helically coiled tubes at high pressure[J]. Annals of Nuclear Energy, 2018, 113: 409-419.
[9] Xiao Y, Hu Z, Chen S, et al. Experimental study of two-phase frictional pressure drop of steam-water in helically coiled tubes with small coil diameters at high pressure[J]. Applied Thermal Engineering, 2018, 132: 18-29.
[10] Xiao Y, Hu Z, Chen S, et al. Experimental investigation and prediction of post-dryout heat transfer for steam-water flow in helical coils[J]. International Journal of Heat and Mass Transfer, 2018, 127: 515-525.
[11] Chen S, Xiao Y, Gu H. Experimental study on heat transfer to water in a three-rod bundle with spacer grids[C]//Proceedings of the 9th International Symposium on Super-Critical Water-cooled Reactors, Vancouver, Canada. March 10-14, 2019.
[12] Hu Z X, Chen S, Gu H Y. Studies on heat transfer of water during depressurizing transient
from supercritical to subcritical pressure[C]//Proceedings of the 9th International
Symposium on Supercritical Water-Cooled Reactors, Vancouver, Canada. March 10-14, 2019.
[13] Xiao Y, Hu Z, Chen S, et al. Experimental investigation of post-dryout heat transfer for steam-water flow in helical coils[C]//Proceedings of the 26th International Conference on Nuclear Engineering, London, UK, July 22-26, 2018.
[14] Chen S, Hu Z, Xiao Y, et al. Experimental study of subcooled boiling heat transfer in helical coils[C]//Proceedings of the 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Xi`an, China, September 3–8, 2017.
[15] 陈硕, 肖瑶, 顾汉洋. 棒束近临界压力区过冷沸腾传热试验研究[C]. 中核核反应堆热工水力技术重点实验室2018年度学术年会, 四川成都, 2018.
[16] 陈硕, 顾汉洋. 堆芯整体水力学试验模拟分析[C]. 中核核反应堆热工水力技术重点实验室2017年度学术年会, 山东荣成, 2017.

第十五届全国反应堆热工流体会议优秀论文奖