苟军利
1.职称：副教授
2.研究方向：反应堆热工及安全
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
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] 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, 2011, in press.
[2] 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.
[3] 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.
[4] 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.
[5] 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.
[6] 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.
[7] J.L. Gou, Y. Ishiwatari, Y. Oka, M. Yamakawa, CFD analyses in tight-lattice subchannels and seven-rods bundle geometries of a super fast reactor, Proceedings of ICAPP ’09, May 10-14, 2009,Tokyo, Japan, paper 9262.
[8] J.L. Gou, Y. Ishiwatari, Y. Oka, M. Yamakawa, Research and development of a Super Fast Reactor, (5) Thermal hydraulic analyses of tight-lattice subchannels, 16th Pacific Basin Nuclear Conference (16PBNC), Oct. 13-18, 2008, Aomori, Japan,P16P1294.
[9] J.L. Gou, S.Z. Qiu, G.H. Su, D.N. Jia, Natural circulation characteristics of an integral pressurized water reactor, 14th International Conference on Nuclear Engineering, July 17-20, 2006, Miami, USA.
[10] J.L. Gou, S.Z. Qiu, D.N. Jia, P. Fan, Thermal hydraulic analysis of a passive residual heat removal system, 13th International Conference on Nuclear Engineering, May 16-20, 2005, Beijing, China.