田瑞峰

Ruifeng Tian, male, born in 1975, professor, doctoral supervisor, who graduated from Harbin Engineering University with a bachelor's degree in thermal energy engineering in 1997, received a master's degree in nuclear energy science and engineering in 2002, and a doctorate in nuclear energy science and engineering in 2005. From 2008.10 to 2009.1, he conducted visiting academic research in the Department of Applied Quantum Physics and Nuclear Energy Engineering, College of Engineering, Kyushu University, Japan. From 2011.8 to 2012.8, he conducted visiting academic research in the Nuclear Engineering Department of Texas A&M University in the United States. As the project leader, he has undertaken more than 10 corporate entrusted projects involving various national special backgrounds from the Nuclear Power Institute, the Institute of Atomic Energy and other units. Hosted 1 key project of National Natural Science Foundation of China, completed 2 projects of the National Natural Science Foundation of China, 20 vertical projects such as National Major Special Projects and Key Laboratory Funds, completed projects of the Nuclear Power Institute, the Institute of Atomic Energy, the Shanghai Nuclear Engineering Research and Design Institute, and relevant institutes of China State Shipbuilding Corporation. He has won 5 third prizes of provincial and ministerial science and technology progress awards, published more than 50 academic papers, edited 1 textbook for the 12th Five-Year Plan, and obtained more than 10 invention and utility model patent authorizations. He is currently a member of the Nuclear Energy Professional Expert Committee of China Energy Research Association, a peer review expert of the National Natural Science Foundation of China, and a former Secretary-General of the Heilongjiang Provincial Nuclear Society.

1993.9-1997.7, Harbin Engineering University, Thermal Energy Engineering, Bachelor.
1999.9-2002.7, Harbin Engineering University, Nuclear Energy Science and Engineering, Master.
2002.9-2005.10, Harbin Engineering University, Nuclear Energy Science and Engineering, PhD
2008.10-2009.1, Visiting Scholar, Kyushu University, Nuclear Science and Technology, Japan.
2011.8-2012.8, Texas A&M University, Nuclear Engineering, Postdoctoral Fellow.

1997.7-2002.9, Harbin Engineering University, Department of Power Engineering, Teaching Assistant.
2002.9-2005.9, Harbin Engineering University, School of Power and Nuclear Energy Engineering, Lecturer.
2005.9-2012.9, Harbin Engineering University, College of Nuclear Science and Technology, Associate Professor.
2012.9-2014.9, Harbin Engineering University, College of Nuclear Science and Technology, Professor.
2014.9-Present, Harbin Engineering University, College of Nuclear Science and Technology, Professor (Doctoral Supervisor).
2009.11-2020.12, Harbin Engineering University, College of Nuclear Science and Technology, Associate Dean.
2021.01-Present, Harbin Engineering University, Nuclear Reactor Engineering Laboratory, Director.

1、Nuclear Power Plant and Equipment Performance
2、Reactor Thermal Hydraulics

2023-2026, Research on thermal hydraulic behavior and particle migration and deposition of liquid lead-bismuth alloy in narrow flow channel, National Natural Science Foundation Key Projects of China, Host.
2022-2025, Experimental study on the comprehensive performance of the drip remover component in the reactor, Nuclear Power Institute of China, Host.
2022-2023, Lead-bismuth mechanical principle verification test technical services, China Nuclear Power Technology Research Institute, Host,
2020-2021, Research on flow-induced vibration characteristics of lead-bismuth alloy, Nuclear Power Institute of China, Host,
2019-2020, Three-dimensional numerical simulation study of flow and heat transfer in gas-cooled reactor core, Nuclear Power Institute of China, Host.
2019-2020, Research on refined numerical simulation of once-through steam generator, Nuclear Power Institute of China, Host.
2018, Experimental study on the performance of inertia water tank of low-temperature heating reactor, Institute of Atomic Energy, Host.
2017-2020, Study on the flow and rupture characteristics of liquid film on vertical special-shaped wall under the action of air flow sweep, General Project of the National Natural Science Foundation of China, Host.
2015-2017, Sensitivity test of dryer structural parameters, Shanghai Nuclear Engineering Research and Design Institute/Major special projects, Host.
2014-2016, Research on rotary steam-water separation technology, China Nuclear Power Operation Technology Corporation, Host.
2012-2016, High-efficiency steam-water separation technology, National Energy Administration/ Major special projects, Host.
2009-2011, Research on measuring the humidity of flowing steam using capacitance method, National Natural Science Foundation of China Youth Fund, Host.

1、Proceedings of the 28th International Conference on Nuclear Engineering, ICONE 28, 2021, Online, 2021.8.
2、Proceedings of the 27th International Conference on Nuclear Engineering, ICONE 27, Tsukuba, Japan, 2019. 5.
3、Key Laboratory of Nuclear Reactor System Design Technology 2018 Academic Annual Conference and the 4th International Symposium on Nuclear Safety and Serious Accidents, Chengdu, China, 2018.11.

Recruiting master's and doctoral students, Email: tianruifeng@hrbeu.edu.cn

《Nuclear powered turbine》,《Fluid mechanics》

《Numerical heat transfer》

《Turbine course design》

[1]Sichao Tan, Ruibo Lu, Qingzhu Liu, Fulong Zhao, Ya Zhou, Yuguang Liu, Ruifeng Tian.A visual experimental device for large space jet at the outlet of plate fuel element:Province Heilongjiang,CN113393948B[P].2022-12-13
[2]Xiaochang Li,Ruifeng Tian,Conglin Liu,Chao Jiang,Bo Wang.A virtual volume force momentum source method for fine numerical solution of reactor core:Province Heilongjiang,CN110705184B[P].2022-07-15
[3]Sichao Tan,Kewei Ning,Xianbo Wang,Fulong Zhao,Yuhao He,Qingzhu Liu,Man Xue,Ruifeng Tian.A nuclear-powered propeller aero-engine:Province Heilongjiang,CN113202576B[P].2022-07-12
[4]Ruifeng Tian,Feng Mao,Bowen Chen,Wei He.A visual experimental system for studying the internal mechanism and selection of the corrugated plate separator:Province Heilongjiang,CN107884168B[P].2019-12-10
[5]Ruifeng Tian,Feng Mao,Yixuan Chen,Lanxin Sun.A visual experimental system of corrugated plate dryer:Province Heilongjiang,CN106442442B[P].2019-06-14
[6]Puzhen Gao,Hanying Chen,Jianjun Wang,Xianbing Chen,Zhongyi Wang,Ruifeng Tian,Sichao Tan.A control method for simulating the neutron reactivity feedback process of nuclear reactor based on the thermal hydraulic experimental device simulating the neutron reactivity feedback process of nuclear reactor..:Province Heilongjiang,CN105869685B[P].2017-10-03
[7]Bao Zhou,Puzhen Gao,Jingda Tian,Ruifeng Tian,Sichao Tan.A method for obtaining the overall instantaneous void fraction by using the local instantaneous void fraction:Province Heilongjiang,CN102928026B[P].2015-04-08
[8]Puzhen Gao,Jingda Tian,Bao Zhou,Sichao Tan,Ruifeng Tian.An experimental and measuring device for studying the flow characteristics of two-phase pulsating flow in a rectangular channel:Province Heilongjiang,CN102928319B[P].2014-11-05
[9]Zhijian Zhang,Ruifeng Tian,Ruixia Yu,Zhaojun Li.A corrugated plate separation element:Province Heilongjiang,CN101732930B[P].2012-02-01
[10]Ruifeng Tian,Pengfei Zhang,Puzhen Gao,Sichao Tan,Zhaojun Li.A steam humidity regulating device:Province Heilongjiang,CN101825906B[P].2011-09-14

Ruifeng Tian, Pingan Liu. "Numerical Calculation of Heat Transfer and Fluid Flow", Harbin Engineering University Press, "Twelfth Five-Year Plan" textbook of the Ministry of Industry and Information Technology. 2015.

[1] Chen B, Li J, Mao F, et al. Numerical study on the characteristics of single wetted flat wire with single droplet impact under the disturbance of airflow[J]. Nuclear Engineering and Design, 2019, 345: 74-84.
[2] Chen B, Tian R, Mao F. Analysis of special phenomena of droplet impact on horizontal liquid film at low velocity[J]. Annals of Nuclear Energy, 2020, 136.
[3] Chen B, Wang B, Mao F, et al. Review on separation mechanism of corrugated plate separator[J]. Annals of Nuclear Energy, 2020, 144.
[4] Chen B, Wang B, Mao F, et al. Analysis of liquid droplet impacting on liquid film by CLSVOF[J]. Annals of Nuclear Energy, 2020, 143.
[5] Chen B, Wang B, Mao F, et al. Experimental study of droplet impacting on inclined wetted wall in corrugated plate separator[J]. Annals of Nuclear Energy, 2020, 137.
[6] Du L, Ruifeng T, Xiaoyi L, et al. Numerical simulation and experimental investigation of structural optimization of capacitance sensors for measuring steam wetness with different coaxial cylinders[J]. Nuclear Engineering and Design, 2013, 262: 88-97.
[7] Du L, Tian R, Zhang P, et al. Numerical simulation and experiment investigating the performance of a capacitance sensor measuring the humidity of wet steam[J]. Measurement Science and Technology, 2011, 22(12).
[8] Ke B, Gao P, Wang B, et al. Study on the thermal hydraulic characteristics of a simulated pressurizer during the blowdown process[J]. Annals of Nuclear Energy, 2021, 153.
[9] Ke B, Gao P, Yang W, et al. Study on estimation of break diameter in the small break loss of coolant accident based on NSGA-II[J]. Annals of Nuclear Energy, 2021, 162.
[10] Liu X Y, Tian R F, Gao Y X, et al. A numerical study of wet steam condensation over a corrugated plate separator. 2014: 805-809.
[11] Liu Y, Shi H L, Gui C, et al. Effect of saturated steam carried downward on the flow properties in the downcomer of steam generator[J]. Energies, 2019, 12(19).
[12] Mao F, Lu M, Xie Y, et al. Effects of mixture parameters variation on the performance of corrugated plate dryer[J]. Progress in Nuclear Energy, 2020, 126.
[13] Mao F, Tian R, Chen Y, et al. Re-entrainment in and optimization of a vane mist eliminator[J]. Annals of Nuclear Energy, 2018, 120: 656-665.
[14] Ming Y, Liu K, Zhao F, et al. Dynamic modeling and validation of the 5 MW small modular supercritical CO2 Brayton-Cycle reactor system[J]. Energy Conversion and Management, 2022, 253.
[15] Ru L, Bowen C, Weibing W, et al. Experimental analysis of droplet impacting on inclined wall of the corrugated plate dryer in steam generator of nuclear power plants[J]. Annals of Nuclear Energy, 2022, 172: 109062.
[16] Ru L, Chunyuan Z, Bo W, et al. Experimental study on the influence of drainage tank structure on separation performance of vertical corrugated plate dryer in PWR[J]. Annals of Nuclear Energy, 2022, 177: 109292.
[17] Ru L, Feng M, Bowen C, et al. Influence of the structure of drainage tank on the separation performance of corrugated plate dryer in NPPs: A short communication[J]. Annals of Nuclear Energy, 2022, 169: 108930.
[18] Tian R, Mao X, Gao P, et al. Single-phase computational fluid dynamics applicability for the study of three-dimensional flow in 55 rod bundles with spacer grids[J]. Chinese Journal of Mechanical Engineering (English Edition), 2012, 25(4): 738-744.
[19] Wang B, Chen B, Ke B, et al. Effect of physical property parameters on critical airflow velocity of a corrugated plate dryer[J]. Annals of Nuclear Energy, 2020, 140.
[20] Wang B, Chen B, Ke B, et al. Study on strip-shaped liquid film in the corrugated plate dryer[J]. Annals of Nuclear Energy, 2020, 139.
[21] Wang B, Chen B, Li R, et al. Study on fracture morphology of water film on the wall of vertical corrugated plate under shear of the air flow[J]. Annals of Nuclear Energy, 2020, 136.
[22] Wang B, Chen B, Li R, et al. Analysis of fluctuation and breakdown characteristics of liquid film on corrugated plate wall[J]. Annals of Nuclear Energy, 2020, 135.
[23] Wang B, Chen B, Tian R. Review of research progress on flow and rupture characteristics of liquid film on corrugated plate wall[J]. Annals of Nuclear Energy, 2019, 132: 741-751.
[24] Wang B, Chen B, Wang G, et al. Analysis of influencing factors of rupture phenomenon of liquid film on the wall of corrugated plate dryer[J]. Annals of Nuclear Energy, 2020, 147.
[25] Wang B, Chen B, Wang G, et al. Back propagation (BP) neural network prediction and chaotic characteristics analysis of free falling liquid film fluctuation on corrugated plate wall[J]. Annals of Nuclear Energy, 2020, 148.
[26] Wang B, Chen B, Wen J, et al. Review and Prospect of the Measurement Technology of the Thickness of the Liquid Film on the Wall of the Corrugated Plate Dryer[J]. Frontiers in Energy Research, 2020, 8.
[27] Wang B, Chen B, Wen J, et al. A Mini Review of Research Progress of Nuclear Physics and Thermal Hydraulic Characteristics of Lead-Bismuth Research Reactor in China[J]. Frontiers in Energy Research, 2020, 8.
[28] Wang B, Ke B, Chen B, et al. Study on the size of secondary droplets generated owing to rupture of liquid film on corrugated plate wall[J]. International Journal of Heat and Mass Transfer, 2020, 147.
[29] Wang B, Lu C, Tian R. Characteristics of liquid film rupture at wave plate corner: A short communication[J]. Annals of Nuclear Energy, 2021, 151.
[30] Wang B, Tian R. Study on fluctuation feature and breakdown characteristic of water film on the wall of corrugated plate[J]. International Journal of Heat and Mass Transfer, 2019, 143.
[31] Wang B, Tian R. Judgement of critical state of water film rupture on corrugated plate wall based on SIFT feature selection algorithm and SVM classification method[J]. Nuclear Engineering and Design, 2019, 347: 132-139.
[32] Wang B, Tian R. Investigation on flow and breakdown characteristics of water film on vertical corrugated plate wall[J]. Annals of Nuclear Energy, 2019, 127: 120-129.
[33] Wang B, Tian R. Study on characteristics of water film breakdown on the corrugated plate wall under the horizontal shear of airflow[J]. Nuclear Engineering and Design, 2019, 343: 76-84.
[34] Wang B, Wang G, Chen B, et al. Research on reflux phenomenon of liquid film on the wall of corrugated plate dryer[J]. Annals of Nuclear Energy, 2020, 141.
[35] Wang G, Wang B, Wen J, et al. Investigation on the hydraulic process of inertia tank in the case of pump trips[J]. Nuclear Engineering and Design, 2021, 379.
[36] Wang G, Wang B, Wen J, et al. Scaling analysis for inertia tank based on the cold state of deep pool-type nuclear heating reactor[J]. Annals of Nuclear Energy, 2021, 151.
[37] Wang G, Wang B, Wen J, et al. Experimental study on the hydraulic characteristics of inertia tank after the failure of pump power[J]. Annals of Nuclear Energy, 2021, 151.
[38] Wang G, Yue Z, Sun R, et al. Preliminary study on thermal–hydraulic behavior of loss-of-flow accident in deep pool-type nuclear reactor[J]. Annals of Nuclear Energy, 2022, 170.
[39] Wang W, Zhang M, Cheng K, et al. A coupled model of corrosion of the steam generator heat transfer tube[J]. Nuclear Engineering and Design, 2022, 396.
[40] Wen J, Tian R, Tan S, et al. The weeping characteristic of submerged multi-orifice plate[J]. Chinese Journal of Chemical Engineering, 2020, 28(4): 955-968.
[41] Wen J, Tian R, Tan S, et al. Numerical simulation of gas holdup in nocoalescence media of industrial-scale bubble column[J]. Progress in Nuclear Energy, 2022, 146.
[42] Wu Y, Zhan C, Li D, et al. Multi-objective optimization analysis of corrugated plate dryer[J]. Annals of Nuclear Energy, 2023, 180.
[43] Chen B, Wang B, Mao F, et al. Numerical study on characteristics of single droplet impacting on wetted surface[J]. Experimental and Computational Multiphase Flow, 2021, 3(1): 59-67.
[44] Wang B, Ke B, Chen B, et al. A technical review of research progress on thin liquid film thickness measurement[J]. Experimental and Computational Multiphase Flow, 2020, 2(4): 199-211.

Ruifeng Tian, Research on Thermal Hydraulic Mechanism of Nuclear Reactor under Movement Conditions,？ 2017, Second Prize of Heilongjiang Province Natural Science and Technology Award.
Ruifeng Tian, Saturated Steam Turbine Monitoring Technology, 2002, Third Prize of Heilongjiang Province Science and Technology Progress Award.