Hanyang Gu
Shanghai Jiao Tong University
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Featured researches published by Hanyang Gu.
2017 25th International Conference on Nuclear Engineering | 2017
Yong Mei; Yechen Zhu; Botao Zhang; Shengjie Gong; Hanyang Gu
External reactor vessel cooling (ERVC) is the key technology for In-Vessel Retention (IVR) to ensure the safety of a nuclear power plant (NPP) under severe accident conditions. The thermal margin of nucleate boiling heat transfer on the reactor pressure vessel (RPV) lower head is important for ERVC and of wide concern to researchers. In such boiling heat transfer processes, the reactor vessel wall inclination effect on the heat transfer coefficient (HTC) and critical heat flux (CHF) should be considered. In this study, experiments were performed to investigate the effects of heater material and surface orientation on the HTC and CHF of nucleate boiling. Copper and stainless steel (SS) surfaces were used to perform boiling tests under atmosphere pressure. The orientation angle of both boiling surfaces were varied between 0° (upward) and 180° (downward). The experimental results show that the surface orientation effects on the HTC is slight for both the copper surface and the SS surface. In addition, the relationship of measured CHF values with the inclination angles was obtained and it shows that the CHF value changes little as the inclination angle increases from 0° to 120° but it decreases rapidly as the orientation angle increases towards 180° for both boiling surfaces. The material effect on CHF is also observed and the copper surface has higher CHF value than the SS surface. Based on the experimental data, a correlation for CHF prediction is developed which includes both the surface orientation effect and the heater material effect.Copyright
2013 21st International Conference on Nuclear Engineering | 2013
Hongbo Li; Meng Zhao; Hanyang Gu; Fei Wang; Jianmin Zhang; Yong Zhang; Jue Yang
The experimental research of supercritical water heat transfer has been performed on the supercritical water multipurpose test loop (SWAMUP) with tube, annular channel, and bundles. The normal heat transfer, heat transfer deterioration (HTD) and heat transfer enhancement were observed; and the heat transfer experimental data were obtained. The experimental results show that: the first kind of HTD caused by buoyancy effect only occurs with low mass flow velocity and high heat flux when the fluid temperature is below pseudo-critical point in all the tested channels and the second kind of HTD caused by acceleration effect always occurs when the fluid temperature reaches pseudo-critical point in tube and annular channel; the heat transfer enhancement occurs when the fluid temperature reaches pseudo-critical point with low mass flow velocity in tube; and the heat transfer enhancement in bundles is caused by the space grids. It is concluded that the heat transfer in bundles is better than in other tested channels.Copyright
Nuclear Engineering and Design | 2012
Ge Zhang; Hao Zhang; Hanyang Gu; Yanhua Yang; Xu Cheng
Nuclear Engineering and Design | 2014
Siyu Zhang; Hanyang Gu; Xu Cheng; Zhenqin Xiong
Nuclear Engineering and Design | 2008
Hanyang Gu; Xu Cheng; Y.H. Yang
Nuclear Engineering and Design | 2011
Xu Cheng; X.J. Liu; Hanyang Gu
Nuclear Engineering and Design | 2010
Hanyang Gu; Xu Cheng; Y.H. Yang
Progress in Nuclear Energy | 2015
Zhenqin Xiong; Cheng Ye; Minglu Wang; Hanyang Gu
Annals of Nuclear Energy | 2015
Zhenqin Xiong; Minglu Wang; Hanyang Gu; Cheng Ye
Nuclear Engineering and Design | 2014
Zhenqin Xiong; Hanyang Gu; Minglu Wang; Ye Cheng