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[1] W. Zhang, Y. Xiao, Y. Ye, C. Hu, Z. Jia, C. Wang, L. Yu, H. Gu, Experimental investigation of side-discharge sparger on pressure oscillation in steam jet condensation, Applied Thermal Engineering, (2023).
[2] H. Zhang, Y. Xiao, X. Yan, H. Gu, Experimental investigation on interfacial parameters of two-phase flow in a tight lattice rod bundle with optimized data processing method, International Communications in Heat and Mass Transfer, 140 (2023).
[3] L. Liu, D. Zhu, M. Liu, D. Li, H. Guo, Y. Xiao, H. Gu, Investigation of the safety limits and the limiting safety system settings on a super carbon-dioxide cooled micro modular reactor, Annals of Nuclear Energy, 180 (2023).
[4] J. Li, Y. Xiao, T. Cong, Z. Xiong, H. Gu, Numerical analysis of the subcooled boiling phenomena in a wire-wrapped annulus, International Journal of Heat and Mass Transfer, 201 (2023).
[5] J. Fu, Y. Xiao, J. Li, Q. Zhang, T. Cong, H. Gu, Development of a Refined Helical Fuel Mixing Model and Application to a Helical Fuel Rod Bundle, Science China-Technological Sciences, (2023).
[6] T. Cong, Q. Zhang, J. Zhu, Y. Xiao, H. Guo, H. Gu, Transverse mixing characteristics of single-phase flow in the helical cruciform fuel assembly, Annals of Nuclear Energy, 180 (2023).
[7] M. Cai, T. Cong, Y. Xiao, H. Gu, Preliminary Thermal-Mechanical coupled modeling of U-10Mo helical cruciform fuel rods under the unirradiated and irradiated conditions, Annals of Nuclear Energy, 181 (2023).
[8] H. Zhao, Q. Zhang, H. Gu, Y. Xiao, M. Liu, CFD investigation on thermal-hydraulic characteristics of a helical cruciform fuel bundle, Progress in Nuclear Energy, 148 (2022).
[9] H. Zhao, H. Gu, M. Liu, Y. Xiao, Numerical investigation of transverse flow and turbulent mixing in a helical cruciform fuel bundle, Annals of Nuclear Energy, 169 (2022).
[10] Q. Zhang, T. Cong, Y. Xiao, J. Li, C. Zeng, H. Gu, Comparison on the thermal–hydraulic characteristics of wire-wrapped fuel and helical cruciform fuel by numerical simulation, Annals of Nuclear Energy, 177 (2022).
[11] Z. Xu, M. Liu, C. Chen, Y. Xiao, H. Gu, Development of an analytical model for the dryout characteristic in helically coiled tubes, International Journal of Heat and Mass Transfer, 186 (2022).
[12] Z. Xu, M. Chao, W. Zhang, F. Zhang, Y. Xiao, M. Liu, H. Gu, Experimental and Numerical Study of the Thermal Hydraulics Characteristics of a Helical-Coiled Once-Through Steam Generator, Applied Thermal Engineering, (2022).
[13] Y. Xiao, J. Li, G. Ding, B. Liu, H. Gu, Numerical study of spacer-induced heat transfer impairment in mixed and free convection heat transfer of water upward flow, International Communications in Heat and Mass Transfer, 137 (2022).
[14] G. Shi, T. Tan, Y. Xiao, W. Zhang, Y. Zhu, Z. Yan, Symmetry-breaking self-sustained oscillation in nonlinear two-phase flow, International Journal of Heat and Mass Transfer, 199 (2022).
[15] L. Liu, B. Liu, Y. Xiao, H. Gu, H. Guo, Preliminary thermal and mechanical analysis on the reactor core of a new heat pipe cooled reactor applied in the underwater environment, Progress in Nuclear Energy, 150 (2022).
[16] J. Li, C. Zhang, Q. Zhang, P. Yang, F. Gan, S. Chen, Z. Xiong, Y. Xiao, H. Gu, Experimental investigation on onset of nucleate boiling and flow boiling heat transfer in a 5 × 5 rod bundle, Applied Thermal Engineering, 208 (2022).
[17] J. Li, Y. Xiao, G. Ding, Z. Xiong, H. Gu, Numerical analysis of the three-dimensional flow phenomena in a 19-pin wire-wrapped tight lattice bundle, International Journal of Heat and Mass Transfer, 196 (2022).
[18] J. Li, Z. Qi, K. Cao, M. Liu, Z. Yang, Y. Xiao, Z. Xiong, H. Gu, Experimental investigation on the heat removal capacity of secondary side passive residual heat removal system for an integrated reactor, Applied Thermal Engineering, 204 (2022).
[19] T. Cong, R. Zhang, B. Wang, Y. Xiao, H. Gu, Single-phase flow in helical cruciform fuel assembly with conjugate heat transfer, Progress in Nuclear Energy, 147 (2022).
[20] T. Cong, Y. Xiao, B. Wang, H. Gu, Numerical study on the boiling heat transfer and critical heat flux in a simplified fuel assembly with 2×2 helical cruciform rods, Progress in Nuclear Energy, 145 (2022).
[21] T. Cong, J. Gong, Y. Xiao, H. Gu, Numerical study on the effects of guide thimble on critical heat flux in a 5 × 5 fuel assembly, Annals of Nuclear Energy, 175 (2022).
[22] Q. Zhang, L. Liu, Y. Xiao, J. Fu, H. Gu, Experimental study on the transverse mixing of 5 × 5 helical cruciform fuel assembly by wire mesh sensor, Annals of Nuclear Energy, 164 (2021).
[23] H. Zhang, Y. Xiao, H. Gu, Interfacial area concentration and bubble size distribution measurement using tomography technique, International Journal of Multiphase Flow, 142 (2021).
[24] H. Zhang, Y. Xiao, H. Gu, Experimental investigation of two-phase flow evolution in a tight lattice bundle using wire-mesh sensor, International Journal of Heat and Mass Transfer, 171 (2021).
[25] Z. Xu, M. Liu, Y. Xiao, H. Gu, Development of a RELAP5 model for the thermo-hydraulic characteristics simulation of the helically coiled tubes, Annals of Nuclear Energy, 153 (2021).
[26] Y. Xiao, W. Zhang, J.L. Li, X.L. Gao, C. Huang, H.Y. Gu, Effects of edge geometry on the flow-induced acoustic resonances in closed side branches, Annals of Nuclear Energy, 160 (2021).
[27] Y. Xiao, J.S. Fu, Q. Zhang, H.B. Zhao, H.Y. Gu, Development of a flow sweeping mixing model for helical fuel rod bundles, Annals of Nuclear Energy, 160 (2021).
[28] J. Li, Y. Xiao, H. Gu, D. Liu, Q. Zhang, Development of a correlation for mixed convection heat transfer in rod bundles, Annals of Nuclear Energy, 155 (2021).
[29] H. Guo, K.Y. Feng, H.Y. Gu, X. Yao, L. Bo, Neutronic modeling of megawatt-class heat pipe reactors, Annals of Nuclear Energy, 154 (2021).
[30] H. Zhang, Y. Xiao, H. Gu, D. Liu, Study on bubbly and cap-bubbly flow in a square channel using dual wire-mesh sensors, International Journal of Multiphase Flow, 133 (2020).
[31] H. Zhang, Y. Xiao, H. Gu, A new method to determine conductivity distribution based on wire-mesh sensor by iteration, Annals of Nuclear Energy, 143 (2020).
[32] Y. Xiao, C. Zhang, H. Gu, Investigation of thermosyphon characteristics in a vertical narrow annulus closed at top with external forced convection cooling, Annals of Nuclear Energy, 138 (2020).
[33] Y. Xiao, J. Li, J. Deng, X. Gao, H. Gu, J. Pan, Study of spacer effects on deteriorated heat transfer of supercritical fluid flow in an annulus, Progress in Nuclear Energy, 123 (2020).
[34] Y. Xiao, C. Huang, J. Li, H. Zhang, H. Gu, Flow-induced acoustic resonances in closed tandem side branches with large diameter, Annals of Nuclear Energy, 149 (2020).
[35] M. Wang, M. Zheng, J. Yan, S. Lin, Y. Xiao, Experimental and numerical studies on two-phase flow instability behavior of a parallel helically coiled system, Annals of Nuclear Energy, 144 (2020).
[36] S. Chen, H. Gu, M. Liu, Y. Xiao, D. Cui, Experimental investigation on heat transfer to supercritical water in a three-rod bundle with spacer grids, Applied Thermal Engineering, 164 (2020) 114466.
[37] H. Zhang, Y. Xiao, H. Gu, Numerical investigations of the accuracy of conductivity wire-mesh sensors, Nuclear Engineering and Design, 345 (2019) 148-156.
[38] S. Chen, Y. Xiao, H. Gu, Experimental study on boiling heat transfer in a three-rod bundle at near-critical pressure, Annals of Nuclear Energy, 131 (2019) 196-209.
[39] S. Chen, D. Liu, Y. Xiao, H. Gu, Experimental study on onset of nucleate boiling and flow boiling heat transfer in a 5 × 5 rod bundle at low flow rate, International Journal of Heat and Mass Transfer, 137 (2019) 727-739.
[40] S. Chen, D. Liu, M. Liu, Y. Xiao, H. Gu, Numerical simulation and analysis of flow and heat transfer in a 5 × 5 vertical rod bundle with buoyancy effects, Applied Thermal Engineering, 163 (2019) 114221.
[41] J. Chen, Z. Xiong, Y. Xiao, H. Gu, Experimental study on the grid-enhanced heat transfer at supercritical pressures in rod bundle, Applied Thermal Engineering, 156 (2019) 299-309.
[42] Y. Xiao, W. Zhao, H. Gu, X. Gao, Effects of branch length and chamfer on flow-induced acoustic resonance in closed side branches, Annals of Nuclear Energy, 121 (2018) 186-193.
[43] Y. Xiao, J. Pan, H. Gu, Numerical investigation of spacer effects on heat transfer of supercritical fluid flow in an annular channel, International Journal of Heat and Mass Transfer, 121 (2018) 343-353.
[44] Y. Xiao, Z. Hu, S. Chen, H. Gu, Experimental investigation and prediction of post-dryout heat transfer for steam-water flow in helical coils, International Journal of Heat and Mass Transfer, 127 (2018) 515-525.
[45] Y. Xiao, Z. Hu, S. Chen, H. Gu, Experimental study on dryout characteristics of steam-water flow in vertical helical coils with small coil diameters, Nuclear Engineering and Design, 335 (2018) 303-313.
[46] Y. Xiao, Z. Hu, S. Chen, H. Gu, Experimental investigation of boiling heat transfer in helically coiled tubes at high pressure, Annals of Nuclear Energy, 113 (2018) 409-419.
[47] Y. Xiao, Z. Hu, S. Chen, H. Gu, Experimental study of two-phase frictional pressure drop of steam-water in helically coiled tubes with small coil diameters at high pressure, Applied Thermal Engineering, 132 (2018) 18-29.
[48] Y. Xiao, H. Gu, X. Gao, H. Zhang, W. Zhao, Flow visualization study of flow-induced acoustic resonance in closed side branches, Annals of Nuclear Energy, 120 (2018) 559-568.
[49] S. Chen, Z. Hu, Y. Xiao, H. Gu, Experimental investigation of subcooled flow boiling heat transfer in helical coils, Nuclear Engineering and Design, 327 (2018) 187-197.
[50] J. Ge, C. Wang, Y. Xiao, W. Tian, S. Qiu, G.H. Su, D. Zhang, Y. Wu, Thermal-hydraulic analysis of a fluoride-salt-cooled pebble-bed reactor with CFD methodology, Progress in Nuclear Energy, 91 (2016) 83-96.
[51] D. Zhang, A. Rineiski, C. Wang, Z. Guo, Y. Xiao, S. Qiu, Development of a kinetic model for safety studies of liquid-fuel reactors, Progress in Nuclear Energy, 81 (2015) 104-112.
[52] Y. Xiao, L.-W. Hu, S. Qiu, D. Zhang, S. Guanghui, W. Tian, Development of a Thermal-Hydraulic Analysis Code and Transient Analysis for a Fluoride-Salt-Cooled High-Temperature Test Reactor, Journal of Nuclear Engineering and Radiation Science, 1 (2015) 7.
[53] H.Y. Gu, Z.X. Hu, D. Liu, Y. Xiao, X. Cheng, Experimental studies on heat transfer to supercritical water in 2 × 2 rod bundle with two channels, Nuclear Engineering and Design, 291 (2015) 212-223.
[54] Y. Xiao, L.-W. Hu, C. Forsberg, S. Qiu, G. Su, K. Chen, N. Wang, Analysis of the Limiting Safety System Settings of a Fluoride Salt–Cooled High-Temperature Test Reactor, Nuclear Technology, 187 (2014) 221-234.
[55] C. Wang, Y. Xiao, J. Zhou, D. Zhang, S. Qiu, G. Su, X. Cai, N. Wang, W. Guo, Computational Fluid Dynamics Analysis of a Fluoride Salt–Cooled Pebble-Bed Test Reactor, Nuclear Science and Engineering, 178 (2014) 86-102.
[56] Y. Xiao, Y. Wu, W. Tian, S. Qiu, G. Su, Development of VTSAS 1.0 and application to an IPWR, Nuclear Engineering and Design, 261 (2013) 20-32.
[57] Z. Guo, D. Zhang, Y. Xiao, W. Tian, G. Su, S. Qiu, Simulations of unprotected loss of heat sink and combination of events accidents for a molten salt reactor, Annals of Nuclear Energy, 53 (2013) 309-319.
[58] Y. Xiao, D. Zhang, Z. Guo, Y. Wu, W. Tian, G. Su, S. Qiu, Numerical analysis for a molten salt reactor in the presence of localized perturbations, Progress in Nuclear Energy, 60 (2012) 61-72.