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苟军利
2023-05-14 18:16
  • 苟军利
  • 苟军利 - 副教授-西安交通大学-动力工程多相流国家重点实验室-个人资料

近期热点

资料介绍

个人简历


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

研究领域


反应堆热工及安全

近期论文


[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.

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