华北电力大学核科学与工程学院讲师；博士研究生；哈尔滨工程大学学士学位、 首尔大学硕士学位、 UST（KAERI Campus）博士学位。
研究方向：
①反应堆热工安全；
②自然循环系统与非能动安全系统相似模化分析。
代表性科研项目：
①作为项目负责人，主持国家自然科学基金青年基金项目一项：基于两流体模型的两相流自然循环水力学相似特性研究；项目编号：**;
②作为项目负责人，主持中央高校基本科研业务专项资金面上项目一项：VDA系统泄压性能特性研究；项目编号：2017MS038。
代表性学术论文：
[1] Xin-Guo Yu, et al., Ki-Yong Choi,“Systematic Analysis of a Station Blackout Scenario for APR1400 with Test Facility ATLAS and MARS Code from Scaling Viewpoint,”Nuclear Engineering and Design, 259(2013): 205-220.
[2] Xin-Guo, Yu, Ki-Yong Choi, et al.,“MARS-KS Code and Sensitivity Analysis of a Pressure Wave Propagation Test Performed in the PMK-2 Test Facility,” Nuclear Technology. 19(2015): 136-150.
[3] Xin-Guo Yu and Ki-Yong Choi,“Systematic and Exact Scaling Analysis of the Single-Phase Natural Circulation Flow: The hydraulic Similarity,”Progress in Nuclear Energy, 89(2016):78-87
[4] X. G. Yu, and K. Y. Choi,“A theoretical model for the single-phase natural circulation flow rate and its assessment against the ATLAS test data.”Progress in Nuclear Energy，97(2017):133-138.
[5] X. G. Yu and K. Y. Choi, “Heat Transfer Scaling Analysis of the Single-Phase Natural Circulation Flow,”Applied Thermal Engineering, 126 (2017): 237-244.
[6] X. G. Yu, “Experiment and Analysis of LOCAs with Different Break Sizes of DVI Line for APR1400 using SNUF,” Master Degree Thesis, Seoul National University, Korea (2010).
[7] X. G. Yu, “Theoretical Scaling Analysis of the Single-Phase and Two-Phase Natural Circulation Flow for Reactor Safety Analysis,” Ph.D. Thesis, University of Science and Technology (KAERI Campus), Korea (2016).
联系邮箱：yxg@ncepu.edu.cn