| Numerical research on thermal mixing characteristics in a 45-degree T-junction for two-phase stratified flow during the emergency core cooling safety injection T Feng, M Wang, P Song, L Liu, W Tian, GH Su, S Qiu Progress in Nuclear Energy 114, 91-104, 2019 | 58 | 2019 |
| Uncertainty analysis of ATF Cr-coated-Zircaloy on BWR in-vessel accident progression during a station blackout Z Guo, R Dailey, T Feng, Y Zhou, Z Sun, ML Corradini, J Wang Reliability Engineering & System Safety 213, 107770, 2021 | 48 | 2021 |
| Numerical research on water hammer phenomenon of parallel pump-valve system by coupling FLUENT with RELAP5 T Feng, D Zhang, P Song, W Tian, W Li, GH Su, S Qiu Annals of Nuclear Energy 109, 318-326, 2017 | 38 | 2017 |
| Numerical approach to study the thermal-hydraulic characteristics of Reactor Vessel Cooling system in sodium-cooled fast reactors P Song, D Zhang, T Feng, S Wang, J Chen, X Xue, Y Zhang, M Wang, ... Progress in Nuclear Energy 110, 213-223, 2019 | 33 | 2019 |
| Quantification of the effect of Cr-coated-Zircaloy cladding during a short term station black out T Feng, J Wang, Y Zhou, P Song, M Wang, R Dailey, W Tian, ... Nuclear Engineering and Design 363, 110678, 2020 | 23 | 2020 |
| Numerical study on the thermal stratification characteristics of AP1000 pressurizer surge line M Wang, T Feng, D Fang, T Hou, W Tian, GH Su, S Qiu Annals of Nuclear Energy 130, 8-19, 2019 | 23 | 2019 |
| Research on the nuclear fuel rods melting behaviors by alternative material experiments Y Li, W Tian, R Chen, T Feng, S Qiu, GH Su Journal of Nuclear Materials 559, 153415, 2022 | 14 | 2022 |
| Thermal hydraulic characteristics analysis of direct residual heat removal system for China pressurized reactor T Feng, M Wang, P Song, W Tian, GH Su, S Qiu Progress in Nuclear Energy 93, 231-237, 2016 | 10 | 2016 |
| Study on three-dimensional numerical simulation of shell and tube heat exchanger of the surface ship under marine conditions Y Liao, Q Cai, S He, M Wang, H Xiao, Z Gong, C Wang, Z Jia, T Feng, ... Nuclear Engineering and Technology 55 (4), 1233-1243, 2023 | 7 | 2023 |
| Numerical study on improved design of passive residual heat removal system for China pressurizer reactor Y Li, P Song, T Feng, M Wang, D Zhang, W Tian, S Qiu Nuclear Engineering and Design 375, 111087, 2021 | 7 | 2021 |
| Spatial temperature distribution of fuel assembly pre-simulation for a new simple core degradation experiment T Feng, W Tian, P Song, J Wang, M Wang, L Li, GH Su, S Qiu Progress in Nuclear Energy 111, 174-182, 2019 | 5 | 2019 |
| Transient characteristics analysis of water hammer phenomena based on coupling program T Feng, W Tian, P Song, D Zhang, G Su, S Qiu Atomic Energy Science and Technology 51 (8), 1364-1370, 2017 | 5 | 2017 |
| Experimental study on fuel rod melting based on alternative materials ZY Wu, K Zhang, T Feng, Y Li, RH Chen, WX Tian, GH Su, SZ Qiu Annals of Nuclear Energy 176, 109286, 2022 | 4 | 2022 |
| Analysis of unsteady flow in compressor cascade based on modal POD methods C Chen, P Song, T Feng, Y Li, Y Liao, C Wang Journal of Physics: Conference Series 2030 (1), 012068, 2021 | 2 | 2021 |
| Analysis of unsteady flow in compressor cascade based on modal DMD methods C Chen, P Song, T Feng, Y Li, Y Liao, C Wang Journal of Physics: Conference Series 2030 (1), 012069, 2021 | 1 | 2021 |
| Numerical Research on Fuel Rod Progression During Core Degradation Process Using MELCOR T Feng, W Tian, P Song, J Wang, M Wang, GH Su, S Qiu International Conference on Nuclear Engineering 51531, V009T16A049, 2018 | 1 | 2018 |
| Experimental Study on Fuel Rod Melting Based on Alternative Material Z WU, K ZHANG, T FENG, R CHEN, W TIAN, S QIU, G SU Atomic Energy Science and Technology 56 (6), 1120-1128, 2022 | | 2022 |
| Comparison of parallel infill sampling criteria for optimization problems T Feng, C Cong, P Song, Y Li, Y Liao, C Wang Journal of Physics: Conference Series 2030 (1), 012067, 2021 | | 2021 |
| Numerical Analysis on the Thermal-Hydraulic Characteristics for the Reactor Main Vessel Cooling System of Chinese Sodium Cooled Fast Reactor P Song, T Feng, D Zhang, L Chen, S Li, Y Lin, S Qiu International Conference on Nuclear Engineering 85253, V002T07A012, 2021 | | 2021 |
| Engineering-level system code for severe accident analysis: MELCOR T Feng, J Wang, X Li, R Dailey, G Vayssier Nuclear Power Plant Design and Analysis Codes, 417-435, 2021 | | 2021 |
