| Applications of ANNs in flow and heat transfer problems in nuclear engineering: a review work T Cong, G Su, S Qiu, W Tian Progress in Nuclear Energy 62, 54-71, 2013 | 148 | 2013 |
| Effects of turbulence models on forced convection subcooled boiling in vertical pipe R Zhang, T Cong, W Tian, S Qiu, G Su Annals of Nuclear Energy 80, 293-302, 2015 | 119 | 2015 |
| Prediction of CHF in vertical heated tubes based on CFD methodology R Zhang, T Cong, W Tian, S Qiu, G Su Progress in Nuclear Energy 78, 196-200, 2015 | 64 | 2015 |
| Study on secondary side flow of steam generator with coupled heat transfer from primary to secondary side T Cong, W Tian, S Qiu, G Su Applied Thermal Engineering 61 (2), 519-530, 2013 | 50 | 2013 |
| Analysis of CHF in saturated forced convective boiling on a heated surface with impinging jets using artificial neural network and genetic algorithm T Cong, R Chen, G Su, S Qiu, W Tian Nuclear engineering and design 241 (9), 3945-3951, 2011 | 45 | 2011 |
| Numerical investigation on local heat transfer characteristics of S-CO2 in horizontal semicircular microtube Y Zhang, M Peng, G Xia, T Cong Applied Thermal Engineering 154, 380-392, 2019 | 39 | 2019 |
| Three-dimensional study on steady thermohydraulics characteristics in secondary side of steam generator T Cong, W Tian, G Su, S Qiu, Y Xie, Y Yao Progress in Nuclear Energy 70, 188-198, 2014 | 35 | 2014 |
| Investigation on the critical heat flux in typical 5 by 5 rod bundle at conditions prototypical of PWR based on CFD methodology R Zhang, T Cong, G Su, J Wang, S Qiu Applied Thermal Engineering 179, 115582, 2020 | 32 | 2020 |
| Numerical prediction of subcooled wall boiling in the secondary side of SG tubes coupled with primary coolant C Wang, T Cong, S Qiu, W Tian, Y Wu, G Su Annals of Nuclear Energy 63, 633-645, 2014 | 32 | 2014 |
| Prediction of falling film evaporation on the AP1000 passive containment cooling system using ANSYS FLUENT code X Wang, H Chang, M Corradini, T Cong, J Wang Annals of Nuclear Energy 95, 168-175, 2016 | 31 | 2016 |
| The role of nuclear energy in the carbon neutrality goal L Liu, H Guo, L Dai, M Liu, Y Xiao, T Cong, H Gu Progress in Nuclear Energy 162, 104772, 2023 | 29 | 2023 |
| CFD analysis on subcooled boiling phenomena in PWR coolant channel R Zhang, T Cong, W Tian, S Qiu, G Su Progress in Nuclear Energy 81, 254-263, 2015 | 29 | 2015 |
| Studies on the subcooled boiling in a fuel assembly with 5 by 5 rods using an improved wall boiling model T Cong, R Zhang, L Chen, X Zhang, T Yu Annals of Nuclear Energy 114, 413-426, 2018 | 27 | 2018 |
| Thermal-hydraulic performance of a PCHE with sodium and sCO2 as working fluids T Cong, Z Wang, R Zhang, B Wang, Y Zhu Annals of Nuclear Energy 157, 108210, 2021 | 24 | 2021 |
| Effects of interaction models on upward subcooled boiling flow in annulus X Zhang, T Yu, T Cong, M Peng Progress in Nuclear Energy 105, 61-75, 2018 | 24 | 2018 |
| Investigation on the critical heat flux in a 2 by 2 fuel assembly under low flow rate and high pressure with a CFD methodology R Zhang, JP Duarte, T Cong, ML Corradini Annals of Nuclear Energy 124, 69-79, 2019 | 23 | 2019 |
| Numerical study on the boiling heat transfer and critical heat flux in a simplified fuel assembly with 2× 2 helical cruciform rods T Cong, Y Xiao, B Wang, H Gu Progress in Nuclear Energy 145, 104111, 2022 | 22 | 2022 |
| Transverse mixing characteristics of single-phase flow in the helical cruciform fuel assembly T Cong, Q Zhang, J Zhu, Y Xiao, H Guo, H Gu Annals of Nuclear Energy 180, 109427, 2023 | 20 | 2023 |
| Simulation analysis of an open natural circulation for the passive residual heat removal in IPWR N Jiang, M Peng, T Cong Annals of Nuclear Energy 117, 223-233, 2018 | 20 | 2018 |
| Effects of power level on thermal-hydraulic characteristics of steam generator T Cong, R Zhang, W Tian, S Qiu, G Su Progress in Nuclear Energy 81, 245-253, 2015 | 19 | 2015 |
