2012.09-2013.09 麻省理工学院 核能科学与工程 联培博士

先进核反应堆热工水力与安全：
1. 多相流与传热
2. 先进燃料组件
3. 多物理多尺度安全分析
4. 先进数据分析方法
课题组招生公告：课题组常年招收本科实习生、硕士生、博士生及博士后。欢迎有志于从事核反应堆热工水力相关领域研究的同学加入团队，有意者请发送个人简历到我的邮箱。

2024-2026 国家优秀青年科学基金项目，核反应堆多尺度物理热工耦合与安全分析，负责人
2023-2026 国家自然科学基金面上项目，瞬变外力场下螺旋管内气液两相流动相界面浓度输运模型研究，负责人
2022-2025 上海市青年科技启明星计划，螺旋金属燃料组件精细化能质传输行为及分析方法研究，负责人
2021-2024 国家自然科学基金面上项目，带绕丝稠密栅棒束通道内混合对流与周向非均匀传热特性研究，负责人
2021-2024 中核集团青年英才菁英计划，海洋核动力堆新型螺旋燃料组件关键热工水力特性研究，负责人
2021-2023 中广核集团，狭小空间内棒束偏离泡核沸腾及交混机理研究，负责人
2020-2022 国家重点研发计划，新型海洋静默式热管核反应堆技术研究，子任务负责人
2020-2022 国家科技重大专项，CHF试验用5×5格架压降及传热试验，负责人
2019-2020 国家科技重大专项，基于5×5棒束试验和19棒束试验的子通道分析软件评估基准题开发，子任务负责人
2019-2020 国家科技重大专项，小型一体化核动力装置中间回路换热性能试验，负责人
2019-2021 国家自然科学基金青年项目，稠密栅内气液两相流动相界面输运模型研究，负责人（结题优秀）
2018-2020 核能开发科研项目，环形燃料组件水力学试验验证，负责人
2016-2017 中广核集团，燃料组件试制件考验试验研究，负责人
2016-2019 上海市青年科技英才扬帆计划，紧密栅内两相流流型及相界面浓度分布特性实验与理论研究，负责人
2015-2017 国家科技重大专项，自主化定型组件零部件水力试验，负责人
2014-2015 中广核集团，波形板干燥器流场CFD分析，负责人

[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.

先进反应堆数值模拟，研究生，48学时
核反应堆热工水力，本科生，51学时
核反应堆物理，本科生，51学时
先进核能系统，本科生，32学时

一种用于螺旋管换热器特性研究的实验系统，发明专利
一种海洋环境影响下熔盐与热管的传热特性实验系统，发明专利
一种抑制蒸汽排放压力振动的装置，发明专利
一种抑制直接接触冷凝压力脉动的装置，发明专利
一种氟盐冷却高温堆非能动余热排出系统自然循环特性模化方法，发明专利
一种线列阵传感器测量误差的修正方法，发明专利
超临界二氧化碳冷却反应堆安全限值计算与瞬态安全分析软件，软著
熔盐冷却球床堆堆芯安全分析软件，软著

International Journal of Advanced Nuclear Reactor Design and Technology, Associate Editor
Nuclear Science and Techniques, Editorial Board Member
Frontiers in Nuclear Engineering, Review Editor
上海市能源研究会，核能专委会委员
中广核研究院-上海交通大学反应堆热工水力联合实验室，主任