2009-2014 Nuclear Science and Engineering, Xi'an Jiaotong University, Doctor
2012-2013 Nuclear Science and Engineering, Massachusetts Institute of Technology, Visiting Doctoral Student
2004-2008 Nuclear Science and Technology, Xi'an Jiaotong University, Bachelor

2024-present Professor, School of Nuclear Science and Engineering, Shanghai Jiao Tong University
2019-2024 Associate Professor, School of Nuclear Science and Engineering, Shanghai Jiao Tong University
2014-2018 Assistant Professor, School of Nuclear Science and Engineering, Shanghai Jiao Tong University

2012-2013 Visiting Doctoral Student, MIT Nuclear Reactor Laboratory, Massachusetts Institute of Technology

Nuclear Reactor Thermal-Hydraulics and Multiphysics Coupling:
1. Multiphase Flow and Heat Transfer
2. Advanced Fuel Assemblies
3. Multiphysics and Multiscale Safety Analysis
4. Advanced Data Analysis Methods

2024-2026 National Natural Science Fund for Excellent Young Scientists, Multi-scale Neutronics and Thermal-hydraulics Coupling and Safety Analysis of Nuclear Reactors, PI
2023-2026 National Natural Science Foundation of China, Investigation of Interfacial Area Transport Equation of Two-Phase Flow in Helical Coils in Transient External Force Fields, PI
2021-2024 National Natural Science Foundation of China, Investigation of Mixed Convection and Circumferential Non-Uniformity Heat Transfer in Wire-Wrapped Tight Lattice Bundles, PI
2019-2021 National Natural Science Foundation of China, Investigation of Interfacial Area Transport Equation of Two-Phase Flow in Tight Lattice Bundles, PI
2016-2019 Shanghai Sailing Program, Investigation of Two-Phase Flow Regime Transition and Interfacial Area Concentration Distribution in Tight Lattice Bundles, PI
2015-2017 National Science and Technology Major Project, Hydraulic Tests of Component Parts of Self-Reliance Fuel Prototype Assembly, PI
2015-2017 National Science and Technology Major Project, Validation Tests of a Acoustic Resonance Analysis Method for Dryers in Steam Generators, PI
2014-2015 China General Nuclear Power Group, CFD Analysis of Dryers with Wave-type Vanes, PI

[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] H. Zhang, Y. Xiao, X. Yan, H. Gu, A two-dimensional void fraction distribution fast prediction model and application to a rod bundle, International Communications in Heat and Mass Transfer, 149 (2023).
[4] C. Zhang, Q. Song, H. Guo, T. Cong, Y. Xiao, H. Gu, Reactivity control optimization of boron-free small modular pressurized water reactor with helical-cruciform metallic fuel, Nuclear Engineering and Design, 414 (2023).
[5] X. Yan, Y. Xiao, H. Zhang, H. Gu, Study of gas-liquid two-phase flow redistribution characteristics in the rod bundle channel using wire-mesh sensor, Chemical Engineering Science, 282 (2023).
[6] X. Yan, Y. Xiao, H. Zhang, H. Gu, Experimental investigation of gas-phase migration behaviors in a tight lattice bundle under two-phase non-equilibrium flow, Chemical Engineering Science, 282 (2023).
[7] X. Yan, Y. Xiao, H. Zhang, H. Gu, Periodic large-scale structural characteristics of two-phase flow in tight lattice bundles, International Journal of Heat and Mass Transfer, 213 (2023).
[8] Y. Wu, Q. Song, R. Wang, Y. Xiao, H. Gu, H. Guo, Development and verification of a Monte Carlo two-step method for lead-based fast reactor neutronics analysis, Nuclear Engineering and Technology, 55 (2023) 2112-2124.
[9] 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).
[10] L. Liu, H. Guo, L. Dai, M. Liu, Y. Xiao, T. Cong, H. Gu, The role of nuclear energy in the carbon neutrality goal, Progress in Nuclear Energy, 162 (2023).
[11] J. Li, Y. Xiao, J. Fu, Q. Zhang, Z. Xiong, H. Gu, Experimental analysis and two-region mixing coefficients development for a wire-wrapped tight lattice bundle, Annals of Nuclear Energy, 191 (2023).
[12] J. Li, Y. Xiao, J. Fu, Z. Xiong, H. Gu, Development of a general flow sweeping mixing model and application to a wire-wrapped assembly, International Communications in Heat and Mass Transfer, 143 (2023).
[13] 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).
[14] X. Jin, Z. Zhang, Y. Sun, M. Liu, Y. Xiao, H. Guo, X. Jiang, L. Chen, H. Gu, Preliminary safety comparison of lead-cooled fast reactors with advanced fuels in unprotected transients, Nuclear Engineering and Design, 411 (2023).
[15] 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, 66 (2023) 586-598.
[16] G. Ding, N. Li, B. Liu, J. Li, Y. Xiao, H. Gu, Numerical study of mixed and free convection heat transfer under ocean conditions, International Journal of Heat and Mass Transfer, 203 (2023).
[17] 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).
[18] M. Cai, T. Cong, Y. Xiao, H. Gu, Multi-physical fuel performance modeling of U-50Zr helical cruciform fuel based on fluid-thermal-structure coupling methodology, Annals of Nuclear Energy, 191 (2023).
[19] 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).
[20] 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).
[21] 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).
[22] 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).
[23] 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).
[24] 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).
[25] 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).
[26] 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).
[27] 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).
[28] 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).
[29] 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).
[30] 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).
[31] 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).
[32] 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).
[33] 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).
[34] 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).
[35] H. Zhang, Y. Xiao, H. Gu, Interfacial area concentration and bubble size distribution measurement using tomography technique, International Journal of Multiphase Flow, 142 (2021).
[36] 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).
[37] 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).
[38] 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).
[39] 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).
[40] 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).
[41] 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).
[42] 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).
[43] 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).
[44] 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).
[45] 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).
[46] 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).
[47] 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).
[48] 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.
[49] H. Zhang, Y. Xiao, H. Gu, Numerical investigations of the accuracy of conductivity wire-mesh sensors, Nuclear Engineering and Design, 345 (2019) 148-156.
[50] 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.
[51] 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.
[52] 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.
[53] 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.
[54] 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.
[55] 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.
[56] 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.
[57] 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.
[58] 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.
[59] 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.
[60] 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.
[61] 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.
[62] 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.
[63] 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.
[64] 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.
[65] 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.
[66] 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.
[67] 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.
[68] 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.
[69] 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.
[70] 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.

Numerical Simulation of Advanced Nuclear Reactors，Postgraduates，51 Hours/3 Credits
Nuclear Reactor Thermal Hydraulics，Undergraduates，51 Hours/3 Credits
Nuclear Reactor Physics，Undergraduates，51 Hours/3 Credits
Introduction of Advanced Nuclear Systems，Undergraduates，32 Hours/2 Credits

Fluoride-salt-cooled High-temperature Reactor Analysis Code (FRAC) V1.0, 2014SR082141

International Journal of Advanced Nuclear Reactor Design and Technology, Associate Editor
Nuclear Science and Techniques, Editorial Board Member
Frontiers in Nuclear Engineering, Review Editor

2024 First Class Prize of Shanghai Science and Technology Progress Award (Rank 2)
2024 China Nuclear Energy Association Innovation Team Award (Principal Investigator)
2024 Yang Fujia Nuclear Science and Technology Youth Talent Award
2023 National Science Fund for Excellent Young Scholars
2023 China Nuclear Energy Association Outstanding Youth Innovation Award
2022 First Class Prize for the Science and Technology Progress Award of China Nuclear Energy Association (Rank 2)

2024 Shanghai Society of Engineering Thermophysics Outstanding Doctoral Thesis Supervisor Award
2024 Shanghai Jiao Tong University First Class Teaching Achievement Award (Rank 6)
2023 China Nuclear Industry Education Society First Prize Outstanding Doctoral Thesis Supervisor Award
2022 Shanghai Municipal Second Class Teaching Achievement Award (Rank 6)