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于新国

  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:11805067;

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(第一或通讯作者)

[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 Energy97(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

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