2009-2014 西安交通大學(xué) 核能科學(xué)與工程 博士
2012-2013 麻省理工學(xué)院 核能科學(xué)與工程 聯(lián)培博士
2004-2008 西安交通大學(xué) 核工程與核技術(shù) 學(xué)士

2024-至今 上海交通大學(xué) 機(jī)械與動(dòng)力工程學(xué)院 教授，博士生導(dǎo)師
2019-2024 上海交通大學(xué) 機(jī)械與動(dòng)力工程學(xué)院 副教授，博士生導(dǎo)師
2014-2018 上海交通大學(xué) 機(jī)械與動(dòng)力工程學(xué)院 講師，博士生導(dǎo)師

核反應(yīng)堆熱工水力與多物理場耦合：
1. 多相流與傳熱
2. 先進(jìn)燃料組件
3. 多物理多尺度安全分析
4. 先進(jìn)數(shù)據(jù)分析方法

課題組招生公告：課題組有新增下年度碩士生、博士生名額。歡迎有志于從事核反應(yīng)堆熱工水力相關(guān)領(lǐng)域研究的同學(xué)加入團(tuán)隊(duì)，有意者請(qǐng)發(fā)送個(gè)人簡歷到我的郵箱。

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

中國核學(xué)會(huì)，核反應(yīng)堆熱工流體力學(xué)分會(huì)理事
中國核學(xué)會(huì)，研究堆與新堆分會(huì)理事
上海市工程熱物理學(xué)會(huì)，理事
上海市能源研究會(huì)，核能專委會(huì)委員
中廣核研究院-上海交通大學(xué)反應(yīng)堆熱工水力聯(lián)合實(shí)驗(yàn)室，主任

2024-2026 國家優(yōu)秀青年科學(xué)基金項(xiàng)目，核反應(yīng)堆多尺度物理熱工耦合與安全分析，負(fù)責(zé)人
2024-2027 上海市科技創(chuàng)新行動(dòng)計(jì)劃，商船用固有安全熔鹽核反應(yīng)堆技術(shù)研究，負(fù)責(zé)人
2023-2026 國家自然科學(xué)基金面上項(xiàng)目，瞬變外力場下螺旋管內(nèi)氣液兩相流動(dòng)相界面濃度輸運(yùn)模型研究，負(fù)責(zé)人
2022-2025 上海市青年科技啟明星計(jì)劃，螺旋金屬燃料組件精細(xì)化能質(zhì)傳輸行為及分析方法研究，負(fù)責(zé)人
2021-2024 國家自然科學(xué)基金面上項(xiàng)目，帶繞絲稠密柵棒束通道內(nèi)混合對(duì)流與周向非均勻傳熱特性研究，負(fù)責(zé)人
2021-2024 中核集團(tuán)青年英才菁英計(jì)劃，海洋核動(dòng)力堆新型螺旋燃料組件關(guān)鍵熱工水力特性研究，負(fù)責(zé)人
2021-2023 中廣核集團(tuán)，狹小空間內(nèi)棒束偏離泡核沸騰及交混機(jī)理研究，負(fù)責(zé)人
2020-2022 國家重點(diǎn)研發(fā)計(jì)劃，新型海洋靜默式熱管核反應(yīng)堆技術(shù)研究，子任務(wù)負(fù)責(zé)人
2020-2022 國家科技重大專項(xiàng)，CHF試驗(yàn)用5×5格架壓降及傳熱試驗(yàn)，負(fù)責(zé)人
2019-2020 國家科技重大專項(xiàng)，基于5×5棒束試驗(yàn)和19棒束試驗(yàn)的子通道分析軟件評(píng)估基準(zhǔn)題開發(fā)，子任務(wù)負(fù)責(zé)人
2019-2020 國家科技重大專項(xiàng)，小型一體化核動(dòng)力裝置中間回路換熱性能試驗(yàn)，負(fù)責(zé)人
2018-2020 核能開發(fā)科研項(xiàng)目，環(huán)形燃料組件水力學(xué)試驗(yàn)驗(yàn)證，負(fù)責(zé)人
2016-2017 中廣核集團(tuán)，燃料組件試制件考驗(yàn)試驗(yàn)研究，負(fù)責(zé)人
2016-2019 上海市青年科技英才揚(yáng)帆計(jì)劃，緊密柵內(nèi)兩相流流型及相界面濃度分布特性實(shí)驗(yàn)與理論研究，負(fù)責(zé)人
2015-2017 國家科技重大專項(xiàng)，自主化定型組件零部件水力試驗(yàn)，負(fù)責(zé)人
2014-2015 中廣核集團(tuán)，波形板干燥器流場CFD分析，負(fù)責(zé)人

[1] Q. Zhang, Z. Liu, Y. Zhang, H. Pang, M. Cai, Z. Hong, G. Yang, H. Wang, L. Liu, Y. Xiao, H. Gu, Experimental study and sub-channel analysis on the transverse mixing of the helical cruciform fuel assembly, Nuclear Engineering and Technology, (2025).
[2] H. Zhang, T. Hibiki, Y. Xiao, H. Gu, Multi-dimensional characteristics of transitional bubbly flow in a tight lattice subchannel, Applied Thermal Engineering, 262 (2025).
[3] X. Yan, Y. Xiao, X. Wang, J. Li, H. Gu, Two-phase flow evolution and interfacial area transport downstream of the mixing-vane spacer grid in rod bundle channels, International Journal of Multiphase Flow, 182 (2025).
[4] Y. Xiao, H. Zhang, X. Yan, H. Gu, Two-group bubble size distribution evolution in vertical two-phase flow: Mechanistic model development and evaluation in a tight-lattice rod bundle, National Science Open, 4 (2025).
[5] Y. Wu, Y. Shen, X. Jin, Q. Song, Y. Xiao, H. Guo, H. Gu, Development of a design method for burnable poisons in small modular fast reactors, Annals of Nuclear Energy, 211 (2025).
[6] X. Wang, M. Liu, R. Zhang, T. Cong, Y. Xiao, H. Gu, Development of a new onset of film boiling model within the fouling layer, Annals of Nuclear Energy, 220 (2025).
[7] X. Wang, M. Liu, J. Fu, X. Yan, H. Tian, T. Cong, Y. Xiao, H. Gu, Pool boiling experimental study on the impact of deposition on the nucleate boiling and bubble behavior of horizontally-placed tubes, International Communications in Heat and Mass Transfer, 164 (2025) 108890.
[8] J. Sun, B. Yuan, G. Ding, J. Fu, Z. Xiong, Y. Xiao, H. Gu, Investigation of buoyancy and spacer effects on heat transfer in low-flow-rate upward flow of Lead-bismuth alloy, International Communications in Heat and Mass Transfer, 164 (2025).
[9] L. Liu, J. Zhang, Z. Liu, Z. Guo, M. Liu, Y. Xiao, H. Gu, Numerical safety analysis on a conceptual design of fluoride-salt-cooled high-temperature reactors under the influence of ocean conditions, Progress in Nuclear Energy, 180 (2025).
[10] J. Li, Y. Xiao, D. Zhu, Q. Zhang, X. Yan, J. Fu, X. Wang, L. Zhang, H. Gu, Experimental and numerical investigation on the circumferential non-uniform heat transfer characteristics in a wire-wrapped tight lattice bundle, International Communications in Heat and Mass Transfer, 162 (2025).
[11] Z. Huang, H. Tian, M. Cai, T. Cong, Y. Xiao, H. Gu, Numerical investigation on boiling crisis characteristic of a 7-rod HCF assembly in hexagonal lattice, Progress in Nuclear Energy, 178 (2025).
[12] G. Huang, J. Fu, C. Liu, Y. Xiao, H. Gu, Development and validation of a subchannel radiative heat transfer model for fuel bundles, Progress in Nuclear Energy, 180 (2025).
[13] J. Fu, Y. Xiao, Z. Wang, Z. Cao, H. Gu, Visualization experimental investigation on flow boiling and critical heat flux characteristics of helical fuel, Annals of Nuclear Energy, 216 (2025).
[14] J. Fu, J. Li, X. Wang, Q. Zhang, Y. Xiao, H. Gu, Development of a general circumferentially nonuniform heat transfer fuel rod model for subchannel analysis and application to helical fuel rods, Science China Technological Sciences, 68 (2025).
[15] K. Feng, Q. Song, Y. Wang, H. Guo, T. Cong, Y. Xiao, H. Gu, Development of a MOC-based multiphysics coupling method for analysis of FCM-fueled micro gas-cooled reactor, Nuclear Engineering and Technology, 57 (2025) 103645.
[16] K. Feng, Q. Song, Y. Shen, L. Lou, Y. Xiao, H. Guo, H. Gu, Development and verification of an MC/MOC two-step scheme for neutronic analysis of FCM-fueled micro gas-cooled reactor, Annals of Nuclear Energy, 211 (2025).
[17] G. Ding, Y. Xiao, H. Gu, Development of a physics-informed coarse-mesh method and applications to the thermohydraulic analysis of rod bundles with mixing vane spacers, Applied Energy, 391 (2025).
[18] S. Chen, C. Zeng, Y. Xiao, H. Gu, Experimental study of spacer effects on post-dryout heat transfer in a tight-lattice rod bundle, Progress in Nuclear Energy, 184 (2025).
[19] S. Chen, J. Fu, Q. Gao, Y. Sun, Y. Xiao, T. Cong, H. Gu, Subchannel analysis of post-dryout flow and heat transfer in a tight-lattice fuel assembly, Annals of Nuclear Energy, 218 (2025).
[20] S. Chen, T. Cong, Y. Xiao, H. Gu, P. Xu, Study on dryout characteristics in a 3-rod tight-lattice bundle, Progress in Nuclear Energy, 185 (2025).
[21] W. Zhang, J. Fu, J. Cui, X. Meng, S. Chen, L. Yu, Y. Xiao, H. Gu, Experimental investigation and prediction of CHF in wire-wrapped rod bundles, Applied Thermal Engineering, 246 (2024).
[22] Q. Zhang, H. Wang, J. Li, C. Li, F. Qi, Y. Zhou, H. Gu, T. Cong, Y. Xiao, Numerical simulation of flow and heat transfer phenomenon of helical cruciform fuel assembly under subcooled boiling, Progress in Nuclear Energy, 175 (2024).
[23] H. Zhang, Y. Xiao, H. Gu, Fully developed pipeline flow fast simulation model and application to a rod bundle subchannel, Annals of Nuclear Energy, 202 (2024).
[24] H. Zhang, T. Hibiki, Y. Xiao, H. Gu, Some characteristics of air-water two-phase flow in the subchannel of a tight lattice rod bundle, International Communications in Heat and Mass Transfer, 159 (2024).
[25] H. Zhang, T. Hibiki, Y. Xiao, H. Gu, Two-group drift-flux model in tight lattice subchannel, International Communications in Heat and Mass Transfer, 159 (2024).
[26] X. Yan, Y. Xiao, X. Wang, J. Li, H. Gu, Two-phase flow evolution and interfacial area transport downstream of the non-mixing vane spacer grid in rod bundle channels, International Communications in Heat and Mass Transfer, 159 (2024).
[27] Y. Sun, Y. Xiao, J. Li, J. Fu, M. Liu, H. Guo, X. Tian, X. Jiang, L. Chen, H. Gu, Development and application of a refined subchannel analysis code for lead-based wire-wrapped bundles, Annals of Nuclear Energy, 208 (2024).
[28] L. Liu, D. Zhu, M. Liu, D. Li, J. Fu, H. Guo, Y. Xiao, H. Gu, Transient analysis of the safety characteristics on a super carbon-dioxide cooled micro modular reactor, Nuclear Engineering and Design, 417 (2024).
[29] L. Liu, C. Shen, M. Liu, Y. Xiao, T. Cong, H. Gu, Numerical simulation of the thermal-hydraulic characteristics of the liquid metal flow across the single-start helical coiled tube bundles, Progress in Nuclear Energy, 173 (2024).
[30] L. Liu, Z. Liu, J. Zhang, C. Shen, M. Liu, Y. Xiao, H. Gu, Numerical research on the influence of ocean conditions on the transient response of passive decay heat removal system of the floating Fluoride-Salt-Cooled High-Temperature Reactors, Annals of Nuclear Energy, 206 (2024) 110653.
[31] H. Guo, S. Han, X. Jin, Y. Wu, Q. Song, Y. Xiao, H. Gu, Pareto front of sodium void worth and breeding ratio in metal-fueled sodium fast reactor with axially heterogeneous core design by coupling neutronics and genetic algorithm, Nuclear Engineering and Design, 429 (2024).
[32] J. Fu, J. Li, L. Zhang, Q. Zhang, Y. Xiao, H. Gu, General flow sweeping mixing model for subchannel analysis and application to three rod bundles with different typical spacer methods, International Communications in Heat and Mass Transfer, 158 (2024).
[33] J. Fu, J. Li, Z. Wang, T. Cong, H. Guo, Y. Xiao, H. Gu, Numerical study of the effect of helical fuel rod geometry on single-phase flow and heat transfer characteristics, Annals of Nuclear Energy, 205 (2024).
[34] T. Cong, Y. Liu, M. Liu, Y. Xiao, H. Gu, Corrosion products deposition and its effects on conjugate heat transfer for helical cruciform fuel assembly, Progress in Nuclear Energy, 168 (2024).
[35] S. Chen, R. Zhang, M. Liu, H. Guo, Y. Xiao, T. Cong, H. Gu, Numerical study on the thermohydraulics of near-critical water in rod bundle with spacer grids, Progress in Nuclear Energy, 177 (2024).
[36] M. Cai, T. Cong, Y. Xiao, H. Gu, Multi-physics coupling behaviors on 3 × 3 helical cruciform fuel rods of U-50Zr alloy under normal and accident conditions, Annals of Nuclear Energy, 206 (2024) 110614.
[37] 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).
[38] 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).
[39] 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).
[40] 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).
[41] 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).
[42] 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).
[43] 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) 124331.
[44] 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.
[45] 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).
[46] 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).
[47] 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).
[48] 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).
[49] 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).
[50] 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).
[51] 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.
[52] 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).
[53] 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).
[54] 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).
[55] 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).
[56] 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).
[57] 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).
[58] 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).
[59] 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).
[60] 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).
[61] 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).
[62] 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).
[63] 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).
[64] 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).
[65] 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).
[66] 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).
[67] 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).
[68] 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).
[69] 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).
[70] 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).
[71] H. Zhang, Y. Xiao, H. Gu, Interfacial area concentration and bubble size distribution measurement using tomography technique, International Journal of Multiphase Flow, 142 (2021).
[72] 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).
[73] 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).
[74] 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).
[75] 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, 160 (2021).
[76] 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).
[77] 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).
[78] 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).
[79] 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).
[80] 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).
[81] 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).
[82] 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).
[83] 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).
[84] 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.
[85] H. Zhang, Y. Xiao, H. Gu, Numerical investigations of the accuracy of conductivity wire-mesh sensors, Nuclear Engineering and Design, 345 (2019) 148-156.
[86] 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.
[87] 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.
[88] 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.
[89] 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.
[90] 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.
[91] 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.
[92] 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.
[93] 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.
[94] 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.
[95] 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.
[96] 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.
[97] 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.
[98] 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.
[99] 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.
[100] 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.
[101] 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.
[102] 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.
[103] 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.
[104] 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.
[105] 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.
[106] 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.

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