苟军利
1.职称：教授，博士生导师
2.研究方向：反应堆热工及安全，先进核能系统及非能动安全技术，最佳估算加不确定性分析方法，先进两相流数值方法及其在反应堆热工及安全分析中应用
3.学习和工作经历：
2010.5-至今：西安交通大学能动学院核能系，副教授和教授
2007.4—2010.3：东京大学大学院工学系研究科，博士后研究员
2003.9—2006.12： 西安交通大学能动学院核能系，工学博士
2000.9—2003.6： 西安交通大学能动学院核能系，工学硕士
1996.9—2000.7： 西安交通大学能动学院核能系，工学学士
4.主要论文：
[1] 单建强，廖承奎，苟军利，冉旭和吴攀，压水堆核电厂瞬态安全数值分析方法，西安交通大学出版社，2016.
[2] Junli Gou, Baoijng Wang and Jianqiang Shan, Development of an analytical model for pure vapor downflow condensation in a vertical tube, Nuclear Engineering and Design, Volume 320, 2017, 346-360.
[3] Junli Gou, Haifu Ma, Zijiang Yang and Jianqiang Shan. An assessment of heat transfer models of water flow in helically coiled tubes based on selected experimental datasets. Annals of Nuclear Energy, Volume 110, December 2017, 648-667.
[4] Junli Gou, Haifu Ma, Zijiang Yang and Jianqiang Shan. Analysis of loss of residual heat removal system for CPR1000 under cold shutdown operation. Annals of Nuclear Energy,Volume 105, 2017,Pages 25-35.
[5] Tianyu Lu, Jianqiang Shan, Junli Gou and et.al., Preliminary safety analysis on loss of flowaccidents and external source transients for LBE cooled ADSR core，PROGRESS INNUCLEAR ENERGY，2016.04.01，88：134~146.
[6] Pan Wu，Jianqiang Shan，Junli Gou ，Laurence K.H. Leung，BinZhang，Bo Zhang，Heat transfer effectiveness for cooling of Canadian SCWR fuelassembly under the LOCA/LOECC scenario，Annals of Nuclear Energy，2015.07.01，81：306~319
[7] WU Pan，SHAN Jian-Qiang，GOU Jun-Li，ZHANG Bin，ZHANG Bo，WANGHe-Nan，No-core-melt assessment for Canadian-SCWR under LOCA/LOECC，Nuclearscience and techniques，2015.10.01，26（2）：59~66.
[8] Pan Wu，Junli Gou，Jianqiang Shan，Bo Zhang，Xiang Li，Preliminarysafety evaluation for CSR1000 with passive safety system，Annals of NuclearEnergy，2014.04.01，65：390~401.
[9] Pan Wu，Junli Gou，Jianqiang Shan，Yang Jiang，Jue Yang，Bo Zhang，Safety analysis code SCTRAN development for SCWR and its application to CGNPCSCWR，Annals of Nuclear Energy，2013.06.01，56（6）：122~135.
[10] J.L. Gou, Y. Ishiwatari, Y. Oka, M. Yamakawa, CFD analyses in tight-lattice subchannels and seven-rod bundle geometries of a Super Fast Reactor, Nuclear Engineering and Design, Volume 241, May 2011,Pages 1656-1666.
[11] J.L. Gou, Z. Shang, Y. Ishiwatari, Y. Oka, M. Yamakawa, S. Ikejiri, CFD analysis of heat transfer in subchannels of a Super Fast Reactor, Nuclear Engineering and Design, Vol. 240, Issue 7, 1819-1829.
[12] J.L. Gou, S.Z. Qiu, G.H. Su，D.N. Jia, Thermal hydraulic analysis of a passive residual heat removal system for an integral pressurized water reactor, Science and Technology of Nuclear Installations, Volume 2009, Article ID 473795.
[13] J.L. Gou, S.Z. Qiu, G.H. Su, D.N. Jia, Theoretical investigation on steady-state natural circulation characteristics of a new type of pressurized water reactor, Nuclear Science and Techniques, 2006, Vol.17, No.5, 314–320.
[14] G.H. Su, J.L. Gou, S.Z. Qiu, X.Q. Yang, D.N. Jia, Theoretical calculation of annular upward flow in a narrow annuli with bilateral heating, Nuclear Engineering and Design, 2003, Vol.225, Issues 2-3, 219-247.
[15] G.H. Su, J.L. Gou, K. Fukuda, D.N. Jia, A theoretical model of annular upward flow in vertical annulus gap, Journal of Nuclear Science and Technology, 2003, Vol.40, No.1, 1-11.
