Selected Publications
[1] 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).
[2] 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).
[3] Y. Xiao, W. Zhang, J. Li, X. Gao, C. Huang, H. Gu, Effects of edge geometry on the flow-induced acoustic resonances in closed side branches, Annals of Nuclear Energy, 160 (2021).
[4] Y. Xiao, J. Fu, Q. Zhang, H. Zhao, H. Gu, Development of a Flow Sweeping Mixing Model for Helical Fuel Rod Bundles, Annals of Nuclear Energy, (2021).
[5] 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).
[6] H. Guo, K.Y. Feng, H.Y. Gu, Y. Xiao, B. Liu, Neutronic modeling of megawatt-class heat pipe reactors, Annals of Nuclear Energy, 154 (2021).
[7] H.W. Zhang, Y. Xiao, H.Y. 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).
[8] H.W. Zhang, Y. Xiao, H.Y. Gu, A new method to determine conductivity distribution based on wire-mesh sensor by iteration, Annals of Nuclear Energy, 143 (2020).
[9] Y. Xiao, C.Z. Zhang, H.Y. Gu, Investigation of thermosyphon characteristics in a vertical narrow annulus closed at top with external forced convection cooling, Annals of Nuclear Energy, 138 (2020).
[10] Y. Xiao, J.L. Li, J. Deng, X.L. Gao, H.Y. Gu, J.S. Pan, Study of spacer effects on deteriorated heat transfer of supercritical fluid flow in an annulus, Progress in Nuclear Energy, 123 (2020).
[11] Y. Xiao, C. Huang, J.L. Li, H.W. Zhang, H.Y. Gu, Flow-induced acoustic resonances in closed tandem side branches with large diameter, Annals of Nuclear Energy, 149 (2020).
[12] M.L. Wang, M.G. Zheng, J.Q. Yan, S.X. 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).
[13] S. Chen, H.Y. Gu, M.L. Liu, Y. Xiao, D.W. Cui, Experimental investigation on heat transfer to supercritical water in a three rod bundle with spacer grids, Applied Thermal Engineering, 164 (2020) 114466.
[14] H.W. Zhang, Y. Xiao, H.Y. Gu, Numerical investigations of the accuracy of conductivity wire-mesh sensors, Nuclear Engineering and Design, 345 (2019) 148-156.
[15] S. Chen, Y. Xiao, H.Y. Gu, Experimental study on boiling heat transfer in a three-rod bundle at near-critical pressure, Annals of Nuclear Energy, 131 (2019) 196-209.
[16] S. Chen, D. Liu, Y. Xiao, H.Y. Gu, Experimental study on onset of nucleate boiling and flow boiling heat transfer in a 5 x 5 rod bundle at low flow rate, International Journal of Heat and Mass Transfer, 137 (2019) 727-739.
[17] S. Chen, D. Liu, M.L. Liu, Y. Xiao, H.Y. Gu, Numerical simulation and analysis of flow and heat transfer in a 5 x 5 vertical rod bundle with buoyancy effects, Applied Thermal Engineering, 163 (2019) 114221.
[18] J. Chen, Z.Q. Xiong, Y. Xiao, H.Y. Gu, Experimental study on the grid-enhanced heat transfer at supercritical Pressures in rod bundle, Applied Thermal Engineering, 156 (2019) 299-309.
[19] Y. Xiao, W. Zhao, H.Y. Gu, X.L. Gao, Effects of branch length and chamfer on flow-induced acoustic resonance in closed side branches, Annals of Nuclear Energy, 121 (2018) 186-193.
[20] Y. Xiao, J.S. Pan, H.Y. 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.
[21] Y. Xiao, Z.X. Hu, S. Chen, H.Y. 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.
[22] Y. Xiao, Z.X. Hu, S. Chen, H.Y. 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.
[23] Y. Xiao, Z.X. Hu, S. Chen, H.Y. Gu, Experimental investigation of boiling heat transfer in helically coiled tubes at high pressure, Annals of Nuclear Energy, 113 (2018) 409-419.
[24] Y. Xiao, Z.X. Hu, S. Chen, H.Y. 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.
[25] Y. Xiao, H.Y. Gu, X.L. 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.
[26] S. Chen, Z.X. Hu, Y. Xiao, H.Y. Gu, Experimental investigation of subcooled flow boiling heat transfer in helical coils, Nuclear Engineering and Design, 327 (2018) 187-197.
[27] J. Ge, C.L. Wang, Y. Xiao, W.X. Tian, S.Z. Qiu, G.H. Su, D.L. Zhang, Y.W. Wu, Thermal-hydraulic analysis of a fluoride-salt-cooled pebble-bed reactor with CFD methodology, Progress in Nuclear Energy, 91 (2016) 83-96.
[28] D.L. Zhang, A. Rineiski, C.L. Wang, Z.P. Guo, Y. Xiao, S.Z. Qiu, Development of a kinetic model for safety studies of liquid-fuel reactors, Progress in Nuclear Energy, 81 (2015) 104-112.
[29] Y. Xiao, L.W. Hu, S.Z. Qiu, D.L. Zhang, G.H. Su, W.X. 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.
[30] H.Y. Gu, Z.X. Hu, D. Liu, Y. Xiao, X. Cheng, Experimental studies on heat transfer to supercritical water in 2 x 2 rod bundle with two channels, Nuclear Engineering and Design, 291 (2015) 212-223.
[31] Y. Xiao, L.W. Hu, C. Forsberg, S.Z. Qiu, G.H. Su, K. Chen, N.X. Wang, Analysis of the Limiting Safety System Settings of a Fluoride Salt-Cooled High-Temperature Test Reactor, Nuclear Technology, 187 (2014) 221-234.
[32] C.L. Wang, Y. Xiao, J.J. Zhou, D.L. Zhang, S.Z. Qiu, G.H. Su, X.Z. Cai, N.X. Wang, W. Guo, Computational Fluid Dynamics Analysis of a Fluoride Salt-Cooled Pebble-Bed Test Reactor, Nuclear Science and Engineering, 178 (2014) 86-102.
[33] Y. Xiao, Y.W. Wu, W.X. Tian, S.Z. Qiu, G.H. Su, Development of VTSAS 1.0 and application to an IPWR, Nuclear Engineering and Design, 261 (2013) 20-32.
[34] Z.P. Guo, D.L. Zhang, Y. Xiao, W.X. Tian, G.H. Su, S.Z. 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.
[35] Y. Xiao, D.L. Zhang, Z.P. Guo, Y.W. Wu, W.X. Tian, G.H. Su, S.Z. Qiu, Numerical analysis for a molten salt reactor in the presence of localized perturbations, Progress in Nuclear Energy, 60 (2012) 61-72.