苟軍利，男，博士，西安交通大學能源與動力學院教授。
基本介紹
- 中文名：苟軍利
- 畢業院校：西安交通大學
- 學位/學歷：博士
- 職業：教師
- 專業方向：核能
- 任職院校：西安交通大學
研究方向,個人經歷,學術成果,
研究方向
反應堆熱工及安全，先進核能系統及非能動安全技術，最佳估算加不確定性分析方法，先進兩相流數值方法及其在反應堆熱工及安全分析中套用
個人經歷
2010.5-至今：西安交通大學能動學院核能系，副教授和教授
2007.4—2010.3：東京大學大學院工學系研究科，博士後研究員
2003.9—2006.12： 西安交通大學能動學院核能系，工學博士
2000.9—2003.6： 西安交通大學能動學院核能系，工學碩士
1996.9—2000.7： 西安交通大學能動學院核能系，工學學士
學術成果
主要論文：
[1]單建強，廖承奎，苟軍利，冉旭和吳攀，壓水堆核電廠瞬態安全數值分析方法，西安交通大學出版社，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,
[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,
[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,
[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.
[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
[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.
[8]Pan Wu，Junli Gou，Jianqiang Shan，Bo Zhang，Xiang Li，Preliminarysafety evaluation for CSR1000 with passive safety system，Annals of NuclearEnergy，2014
[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.
[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
[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
[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,
[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
[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,
[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
