张尧立 副教授

张尧立

厦门大学科技创新创业博士培养项目副组长

厦门大学能源学院副教授，福建省核能工程中心常务副主任、政协第十四届厦门市委员会特邀研究员

邮箱：zhangyl@xmu.edu.cn、zhangyl03@gmail.com

研究方向： 反应堆安全、反应堆热工水力、热力循环主要从事热工水力学的研究。

课题组网站：www.zhangyaoli.top

个人履历：

2017.08-至今 厦门大学 能源学院副教授

2018.11-至今 中国能源研究会核能专业委员会 专家委员

2012.07-2017.08 厦门大学 能源学院 助理教授

2016.10-2017.10 麻省理工学院 核科学与工程学院 访问学者

2007.09-2012.06 清华大学 核能与新能源技术研究院 博士

2003.09-2007.06 清华大学 热能工程系 学士

主持和承担课题项目：

[1] 核电站材料监测管理、失效预防及消除技术的开发和应用 2011/01/01  参与

[2] S-CO2布雷顿循环能量转换系统技术评估 2013/12/01  主要参与

[3] 用于处理废水的低温蒸发系统的优化和仿真 2013/12/17  主持

[4] 行波堆先进燃料循环研究 2014/04/01  主要参与

[5] 西安渭北工业区临潼现代工业组团综合能源项目 2014/04/15  主要参与

[6] 用于四代堆的超临界二氧化碳闭式布雷顿循环系统分析 2015/01/01  主持

[7] 高温气冷堆及主氦风机技术评估 2015/07/01  主持

[8] 核能生物质能系统耦合特性与关键问题 2015/01/01  主持

[9] 蒸汽发生器倒流特性计算分析 2015/11/30 参与

[10] 小型堆换热器设计 2016/01/01  主持

[11] 超临界二氧化碳闭式布雷顿循环瞬态特性分析 2016/01/01  主持

[12] 倾斜窄流道受限滑移汽泡动力学特性及传热机理研究 2016/05/16 参与

[13] S-CO2布雷顿循环能量转换系统技术评估（二期） 2016/07/12 主要参与

[14] 极致安全反应堆研究 016/10/01 主持

[15] 换热设备去污防垢的节能效果评估 2018/04/10 主持

[16] 超临界二氧化碳在拟临界区的对流换热研究 2019/01/01 主持

[17] 系统集成与试验测试技术研究 2020/09/15 主持

[18] 基于CFD方法的质子交换膜燃料电池仿真优化研究 2020/10/01 主持

近5年出版物代表作：

在国内外SCI/EI期刊发表论文20余篇。担任Applied Thermal Engineering, Energy Conversion and Management, Nuclear Science and Engineering, Annals of Nuclear Energy, 厦门大学学报、哈尔滨工程大学学报等SCI/EI期刊审稿人。

[1] Y. Zhang, X. Liu, W. Wei, T. Peng, G. Hong, and C. Meng, “Mobile charging: A novel charging system for electric vehicles in urban areas,” Appl. Energy, vol. 278, p. 115648, 2020.

[2] H. Ding, Y. Zhang*, K. Ye, and G. Hong, “Development of a model for thermal-hydraulic analysis of helically coiled tube once-through steam generator based on Modelica,” Ann. Nucl. Energy, p. 107069, Sep. 2019.

[3] H. Lin, M. He, Q. Jing, W. Yang, S. Wang, Y. Liu, Y. Zhang, et al., “Angle-shaped triboelectric nanogenerator for harvesting environmental wind energy,” Nano Energy, vol. 56, pp. 269–276, Feb. 2019.

[4] K. Ye, Y. Zhang*, L. Yang, Y. Zhao, N. Li, and C. Xie, “Modeling convective heat transfer of supercritical carbon dioxide using an artificial neural network,” Appl. Therm. Eng., vol. 150, pp. 686–695, Mar. 2019.

[5] Z. Li, Y. Zhang*, Q, Gao, et al., “Safety analysis of a small modular reactor using fully ceramic micro-encapsulated fuel,” Prog. Nucl. Energy, vol. 113, pp. 74–83, May 2019.

[6] K. Ye, Y. Zhang*, X. Sheng, N. Li, Y. Yang, and Y. Chen, “Numerical analysis of the flow behavior in a helically coiled once through steam generator,” Nucl. Eng. Des., vol. 330, pp. 187–198, Apr. 2018.

[7] Y. Zhang, J. Buongiorno, M. Golay, N. Todreas, Safety Analysis of a 300-MW(electric) Offshore Floating Nuclear Power Plant in Marine Environment, Nucl. Tech., 203:2 (2018), 129-145, DOI: 10.1080/00295450.2018.1433935

[8] J. Huang, N. Li, Y. Zhang*, J. Lin, Q. Guo, The excess reactivity management in small pressurized water reactor utilizing fully ceramic microencapsulated fuel, Prog. Nucl. Energy. 101 (2017) 251–259. doi:10.1016/j.pnucene.2017.08.005.

[9] Y. Zhang, D. Wang, J. Lin, J. Hao, Development of a Computer Code for Thermal-hydraulic Design and Analysis of Helically Coiled Tube Once-through Steam Generator, Nuclear Engineering and Technology, 2017

[10] J. Huang, N. Li, Y. Zhang*, Q. Guo, J. Zhang, The safety analysis of a small pressurized water reactor utilizing fully ceramic microencapsulated fuel, Nucl. Eng. Des. 320 (2017) 250–257.

[11] Kai Ye, Yaoli Zhang*, Jianshu Lin, Ning Li, Yinglin Yang, Zhuocheng Li, Junwei Hao, Yifen Chen, CFD Analysis of the Primary Side in a Helical-Coil Once-Through Steam Generator, ICONE25, Shanghai, 2017

[12] Yinglin Yang, Qixun Guo, Jianshu Lin, Yaoli Zhang*, Kai Ye, BoShen Bian, Zhuocheng Li, Modeling and Simulating Supercritical CO2 Brayton Cycle in SMR Using Modelica, ICONE25, Shanghai, 2017

[13] D. Liang, Y. Zhang*, C. Fang, Q. Guo, G. Hong, Influence of pressure on the thermal performance of the S-CO2 Brayton cycle, Harbin Gongcheng Daxue Xuebao/Journal Harbin Eng. Univ. 38 (2017) 578–582.

[14] G. Hong, Z. Xu, B. Bian, Y. Zhang, X. Yan, Y. Huang, Predictive Study of Bubble Mean Diameter in Subcooled Flow Boiling, Hedongli Gongcheng/Nuclear Power Eng. 38 (2017).

[15] J. Hao, Y. Zhang*, J. Zheng, Z. Zhou, X. Sheng, G. Hong, K. Ye, N. Li, Analysis of Density Wave Oscillations in Helically Coiled Tube Once-Through Steam Generator, Sci. Technol. Nucl. Install. 2016 (2016) 1–10.

[16] Y. Luo, G. Ran, N. Chen, Q. Shen, Y. Zhang, Microstructural Evolution, Thermodynamics, and Kinetics of Mo-Tm2O3 Powder Mixtures during Ball Milling, Materials (Basel). 9 (2016) 834.

[17] Y. Wang, Y. Yang, Y. Zhang, and Z. Zhou, “Demonstration of simulation analysis program PCCSAP-3D for passive containment cooling system (PCCS),” Hedongli Gongcheng/Nuclear Power Eng., vol. 37, no. 2, pp. 175–179, Apr. 2016. (in Chinese)

[18] D. Liang, Y. Zhang*, Q. Guo, et al., “Modeling and analysis of nuclear reactor system using supercritical-co2 brayton cycle,” Journal of Xiamen University: Natural Science, vol. 54, no. 5, pp. 608-613, 2015. (in Chinese)

[19] J. Huang, Y. Zhang*, Q. Guo, et al., “Studies on the small pressurized water reactor based on triso fuels,” Journal of Xiamen University: Natural Science, vol. 54, no. 5, pp. 603-607, 2015. (in Chinese)

[20] D. Shen, Y. Zhang*, Q. Guo, et al., “Effect factors of keff by using different kinds of materials in travelling wave reactors,” Journal of Xiamen University: Natural Science, vol. 54, no. 5, pp. 614-618, 2015. (in Chinese)

[21] Y. Wang, Y. Zhang, Z. Zhou, H. Xie, and Y. Yang, “Study of the influence of design parameters and initial condition on passive containment cooling system,” Int. Top. Meet. Nucl. React. Therm. Hydraul. 2015, NURETH 2015, vol. 2, pp. 1744–1757, 2015.

编辑:嘉庚创新实验室