基本介紹
- 中文名：張堯立
- 畢業院校：清華大學
- 學位/學歷：博士
- 職業：教師
- 任職院校：廈門大學
個人經歷,研究方向,主講課程,學術成果,課題項目,科研論文,專利和著作權,榮譽獎項,
個人經歷
2012.07-至今 廈門大學 能源學院副教授
2018.11-至今 中國能源研究會核能專業委員會 專家委員
2012.07-2017.08 廈門大學 能源學院 助理教授
2016.10-2017.10 麻省理工學院 核科學與工程學院 訪問學者
2007.09-2012.06 清華大學 核能與新能源技術研究院 博士
2003.09-2007.06 清華大學 熱能工程系 學士
研究方向
極致安全核反應堆、超拒挨微備臨界二氧化碳（sCO2）能量轉換系統
主講課程
第七批線上開放習灶巴課程建設——《中英文科技論文寫作》，中國大學生慕課網，2019.10
學術成果
課題項目
[1] 核電站材料監測管理、失效預防及消除技術的開發和套用2011/01/01 參與
[2] S-CO2布雷頓循環能量轉換系統技術評估 2013/12/01 主要參與
[3] 用於處理廢水的低溫蒸發系統的最佳化和仿真 2013/12/17 主持
[4] 行波堆先進燃料循環研究 2014/04/01 主要參與
[5] 西安渭北工業區臨潼現代工業組團綜合能源項目 2014/04/15 主要參與
[6] 用於四代堆的超臨界二氧化碳閉式布雷頓循環系統分析 2015/01/01 主持
[7] 高溫氣冷堆及主氦風機技術評估 2015/07/01 主持
[8] 核能生物質能系統耦合特性與關鍵問題 2015/01/01 主持灑茅
[9] 蒸汽發生器倒流特性計算分析 2015/11/30 參與
[10] 小型堆換熱器設計 2016/01/01 主持
[11] 超臨界二氧化碳閉式布雷頓循環瞬態特店匪洪邀性分析 2016/01/01 主持
[12] 傾斜窄流道受限滑移汽泡動力學特性及傳熱機理研究 2016/05/16 參與
[13] S-CO2布雷頓循環能犁元邀量轉換系統技術評估（二期）婚榜婚 2016/07/12 主要參與
[14] 極致安全反應堆研究 2016/10/01 主持
[15] 換熱設備去污防垢的節能效果評估2018/04/10 主持
[16] 超捉白歸臨界二氧化碳在擬臨界區的對流換熱研究 2019/01/01 主持
科研論文
[1] 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,Sep. 2019.
[2] 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, Feb. 2019.
[3] 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., Mar. 2019.
[4] Z. Li, Y. Zhang, Q, Gao, et al., “Safety analysis of a small modular reactor using fully ceramic micro-encapsulated fuel,” Prog. Nucl. Energy,May 2019.
[5] 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. Apr. 2018.
[6] 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. (2018)
[7] 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. (2017)
[8] 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
[9] 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.(2017)
[10] 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
[11] 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
[12] D. Liang, Y. Zhang, C. Fang, Q. Guo, G. Hong, Influence of pressure on the thermal performance of the S-CO<inf>2</inf> Brayton cycle, Harbin Gongcheng Daxue Xuebao/Journal Harbin Eng. Univ. (2017)
[13] 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. (2017).
[14] 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)
[15] 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). (2016)
[16] 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., Apr. 2016. (in Chinese)
[17] 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, 2015. (in Chinese)
[18] 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, 2015. (in Chinese)
[19] 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, 2015. (in Chinese)
[20] 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 2015,2015.
專利和著作權
[1] 一種核能和生物質能聯合系統及方法，發明專利，2016年10月
[2] 採用超臨界CO2的小型核反應堆能量轉換系統，實用新型專利，2016年09月
[3] 一種小型反應堆安全殼，實用新型專利，2016年09月
[4] 一種用於製備超臨界二氧化碳石墨烯納米流體的設備，實用新型專利，2017年03月
[5] 一種用於製備超臨界二氧化碳混合工質的系統，實用新型專利，2017年03月
[6] 一種煙氣脫硫脫硝裝置，發明專利，2015年04月
[7] 一種煙氣脫硫脫硝的方法、裝置及其用途，發明專利，2016年05月
[8] 一種鐵基鐵酸鋱材料及其套用，實用新型專利，2016年04月
[9] 一種海上核動力裝置的自動水平調節系統，發明專利，2019年06月
[10] 輕水堆經濟性分析軟體，計算機軟體著作權，2015年04月
[11] 行波堆經濟性分析軟體計算機軟體著作權，2015年04月
[12]超臨界二氧化碳布雷頓循環系統1.0，計算機軟體著作權，2016年06月
[13] 冷水機組製冷係數計算分析軟體，計算機軟體著作權，2019年04月
榮譽獎項
鷺燕獎教金，2019.04
廈門大學第十三屆青年教師教學比賽二等獎，2018
科研論文
[1] 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,Sep. 2019.
[2] 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, Feb. 2019.
[3] 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., Mar. 2019.
[4] Z. Li, Y. Zhang, Q, Gao, et al., “Safety analysis of a small modular reactor using fully ceramic micro-encapsulated fuel,” Prog. Nucl. Energy,May 2019.
[5] 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. Apr. 2018.
[6] 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. (2018)
[7] 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. (2017)
[8] 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
[9] 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.(2017)
[10] 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
[11] 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
[12] D. Liang, Y. Zhang, C. Fang, Q. Guo, G. Hong, Influence of pressure on the thermal performance of the S-CO<inf>2</inf> Brayton cycle, Harbin Gongcheng Daxue Xuebao/Journal Harbin Eng. Univ. (2017)
[13] 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. (2017).
[14] 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)
[15] 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). (2016)
[16] 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., Apr. 2016. (in Chinese)
[17] 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, 2015. (in Chinese)
[18] 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, 2015. (in Chinese)
[19] 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, 2015. (in Chinese)
[20] 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 2015,2015.
專利和著作權
[1] 一種核能和生物質能聯合系統及方法，發明專利，2016年10月
[2] 採用超臨界CO2的小型核反應堆能量轉換系統，實用新型專利，2016年09月
[3] 一種小型反應堆安全殼，實用新型專利，2016年09月
[4] 一種用於製備超臨界二氧化碳石墨烯納米流體的設備，實用新型專利，2017年03月
[5] 一種用於製備超臨界二氧化碳混合工質的系統，實用新型專利，2017年03月
[6] 一種煙氣脫硫脫硝裝置，發明專利，2015年04月
[7] 一種煙氣脫硫脫硝的方法、裝置及其用途，發明專利，2016年05月
[8] 一種鐵基鐵酸鋱材料及其套用，實用新型專利，2016年04月
[9] 一種海上核動力裝置的自動水平調節系統，發明專利，2019年06月
[10] 輕水堆經濟性分析軟體，計算機軟體著作權，2015年04月
[11] 行波堆經濟性分析軟體計算機軟體著作權，2015年04月
[12]超臨界二氧化碳布雷頓循環系統1.0，計算機軟體著作權，2016年06月
[13] 冷水機組製冷係數計算分析軟體，計算機軟體著作權，2019年04月
榮譽獎項
鷺燕獎教金，2019.04
廈門大學第十三屆青年教師教學比賽二等獎，2018
