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[1] 单建强,朱继洲,张斌,压水堆核电厂调试与运行. 北京:中国电力出版社,2009.

[2] 朱继洲,单建强,核电站安全. 北京:中国电力出版社. 2011.

[3] 朱继洲,奚树人,单建强等,核反应堆安全分析. 西安:西安交通大学出版社,北京:原子能出版社. 2004.

[4] 朱继洲,单建强,张斌,压水堆核电厂的运行. 北京:原子能出版社,2008.

[5] Shan JQ, Zhang B, Li CY, Leung LKH 2009. SCWR subchannel code ATHAS development and CANDU-SCWR analysis. Nuclear Engineering and Design 239(10): 1979-1987. SCI:501VO

[6] Li CY, Shan JQ, Leung LKH 2009. Subchannel analysis of CANDU-SCWR fuel. Progress in Nuclear Energy 51(8): 799-804. SCI:504RW

[7] Shan JQ, Chen W, Rhee BW, Leung LKH 2010. Coupled neutronics/thermal-hydraulics analysis of CANDU-SCWR fuel channel. Annals of Nuclear Energy 37(1): 58-65. SCI: 537XG

[8] Shan JQ, Pan J, Jiang Y 2010. Thermal consideration of CANDU-SCWR sliding pressure startup through subchannel analysis. Nuclear Engineering and Design 240(5): 1005-1012. SCI: 585AO

[9] Zhang B, Shan JQ, Jiang J 2010. Numerical analysis of supercritical water heat transfer in horizontal circular tube. Progress in Nuclear Energy 52(7): 678-684. SCI: 619PF

[10] Zhang B, Shan JQ, Jiang J 2010. Numerical Analysis of Supercritical Water Heat Transfer in Vertical Tube with Different Obstacles, Nuclear Science and Techniques, 2010.8. SCI: 674OO

[11] Groeneveld DC, Shan JQ, Vasic AZ, et al. 2007. The 2006 CHF look-up table. Nuclear Engineering and Design 237(15-17): 1909-1922. SCI: 206AT

[12] Shan JQ, Zhang B, Li CY, Leung LKH 2009. SCWR subchannel code ATHAS development and CANDU-SCWR analysis. Nuclear Engineering and Design 239(10): 1979-1987. SCI:501VO
[13] Zhang B, Shan JQ, Jiang J 2010. Numerical analysis of supercritical water heat transfer in horizontal circular tube. Progress in Nuclear Energy 52(7): 678-684. SCI: 619PF
[14] Zhang B, Shan JQ, Jiang J 2010. Simulation of heat transfer of supercritical water in obstacle-bearing vertical tube. Nuclear Science and Techniques 21(4): 241-245. SCI:674OO
[15] 张博, 单建强. 带格架圆管内超临界水竖直向上流动传热强化特性数值分析. 核动力工程 31(S1): 93-96。 EI:20102513031421
[16] Zhang B, Shan J, Jiang J. Turbulent mixing model applicable to supercritical condition. 5th International Symposium on Supercritical Water-Cooled Reactors (SCWR5), Vancouver, British Columbia, Canada, March 13-16, 2011.

[17] 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.
[18] 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.
[19] 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.
[20] 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.
[21] 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.
[22] 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.
[23] 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.
[24] 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.
[25] 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.
[26] 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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