Author

Ruifeng Tian

Observed names: Sichao Tan, TIAN Ruifeng

Institution: Harbin Engineering University

Observed institutions: Harbin Engineering University, Ministry of Industry and Information Technology

ORCID: 0000-0002-6437-5499

Observed ORCID: 0000-0002-6437-5499

OpenAlex ID: A5015979334

Dynamic modeling and validation of the 5 MW small modular supercritical CO2 Brayton-Cycle reactor system

2022 · Yang Ming, Kai Liu, et al. · Energy Conversion and Management · 125

A three-dimensional refined numerical simulation of cross-flow induced vibration mechanism in the tube bundle

2023 · Hai Zhao, Puzhen Gao, et al. · Nuclear Engineering and Design · 22

S–CO2 heat transfer characteristics analysis in PCHE and vertical channel

2022 · Kai Liu, Fulong Zhao, et al. · Progress in Nuclear Energy · 21

Dynamic analysis of the PCHE in 5MWth small modular SCO2 Brayton-Cycle reactor system

2024 · Yang Ming, Haoran Shen, et al. · Nuclear Engineering and Design · 16

Thermal-hydraulic characteristics analysis of unprotected accident and protection control strategy for helium-xenon cooled reactor system

2024 · Haoyang Liao, Xianbo Wang, et al. · Energy · 16

S-CO2 and LBE coupled heat transfer characteristics analysis in new layout PCHE

2024 · Kai Liu, Fulong Zhao, et al. · Nuclear Engineering and Design · 15

Analysis of flow heat transfer characteristics of helium-xenon gas mixtures during natural circulation

2024 · Xianbo Wang, Lin Xie, et al. · Nuclear Engineering and Design · 12

The interaction between cross-flow induced vibration and convection heat transfer in tube bundle at subcritical Reynolds number

2023 · Hai Zhao, Puzhen Gao, et al. · Applied Thermal Engineering · 12

Modeling and safety analysis of supercritical CO2 Brayton cycle reactor system under loss of coolant accident (LOCA)

2024 · Yang Ming, Haoran Shen, et al. · Annals of Nuclear Energy · 11

Modeling and program development of supercritical CO2 sub-channel based on Modelica language

2023 · Jia Guo, Yang Jin, et al. · Applied Thermal Engineering · 11

Study on the flow and heat transfer of LBE in wire-rod and rib-rod bundle channels

2024 · Xianmin Dong, Man Xue, et al. · Annals of Nuclear Energy · 10

Study on ultrasonic attenuation characteristics in air-droplet two-phase flow

2023 · Jiahong Zhu, Yuansheng Lin, et al. · Annals of Nuclear Energy · 9

Transient thermal characteristics analysis of various single line and composite bypass controls for helium-xenon cold reactor Brayton cycle system

2025 · Haoyang Liao, Ersheng You, et al. · Renewable Energy · 8

Experimental study on characteristics of phase distribution in air-water bubbly flow in a rod bundle with spacer grid

2025 · Jiaxing Ren, Ruohao Wang, et al. · Progress in Nuclear Energy · 8

Experimental study of the effect of surface roughness on the heat transfer characteristics of subcooled flow boiling in a narrow rectangular channel

2024 · Yu Zou, Jinyang Li, et al. · Annals of Nuclear Energy · 8

Transient characteristics of supercritical carbon dioxide Brayton cycle system with or without control strategy under accident conditions

2025 · Ziwen Su, Xiaoyu Wang, et al. · Progress in Nuclear Energy · 7

Experimental study on two-phase flow instability in helically coiled tube under rolling motion

2024 · Ruohao Wang, Chao Qi, et al. · Annals of Nuclear Energy · 7

Numerical studies on the effect of surface roughness on flow field and flow-induced vibration in the in-line tube bundle

2024 · Hai Zhao, Yibo Yin, et al. · Nuclear Engineering and Design · 6

Numerical study of bistable flow phenomena in square tube bundles based on Large Eddy Simulation

2025 · Junshuai Sun, Junshuai Sun, et al. · Annals of Nuclear Energy · 5

Numerical study on lead–bismuth cross-flow induced vibration in the elastic tube bundle

2024 · Hai Zhao, Puzhen Gao, et al. · Annals of Nuclear Energy · 5

Characteristics analysis of natural circulation residual heat removal in helium-xenon cooled reactor

2024 · Haoyang Liao, Yufeng Li, et al. · Nuclear Engineering and Design · 4

Experimental study on flux allocation characteristics of annular fuel bundle channel

2025 · Jinyang Li, Shouxu Qiao, et al. · Annals of Nuclear Energy · 3

Investigation of heat transfer characteristics of carbon dioxide transcritical flow in a reactor channel

2025 · Mao Luo, Hui Bao, et al. · Progress in Nuclear Energy · 3

Investigation of containment spraying characteristics based on the correction of droplet evaporation shielding effects

2024 · Fulong Zhao, Ruixuan Wei, et al. · Nuclear Engineering and Design · 3

Physical optimization and safety analysis of space thermionic reactor

2023 · Lin Xie, Zhifang Qiu, et al. · Progress in Nuclear Energy · 3

Works count: 59

Citation count: 380

H-index: 10

I10-index: 11