| A variational nodal approach to 2D/1D pin resolved neutron transport for pressurized water reactors T Zhang, EE Lewis, MA Smith, WS Yang, H Wu Nuclear Science and Engineering 186 (2), 120-133, 2017 | 42 | 2017 |
| Experimental investigation on split-mixing-vane forced mixing in pressurized water reactor fuel assembly J Xiong, W Qu, T Zhang, X Chai, X Liu, Y Yang Annals of Nuclear Energy 143, 107450, 2020 | 38 | 2020 |
| A three-dimensional variational nodal method for pin-resolved neutron transport analysis of pressurized water reactors T Zhang, Y Wang, EE Lewis, MA Smith, WS Yang, H Wu Nuclear Science and Engineering 188 (2), 160-174, 2017 | 37 | 2017 |
| High-fidelity multi-physics coupling study on advanced heat pipe reactor W Xiao, X Li, P Li, T Zhang, X Liu Computer Physics Communications 270, 108152, 2022 | 34 | 2022 |
| Computational fluid dynamics and subchannel analysis of lead–bismuth eutectic-cooled fuel assembly under various blockage conditions XJ Liu, DM Yang, Y Yang, X Chai, JB Xiong, TF Zhang, X Cheng Applied Thermal Engineering 164, 114419, 2020 | 30 | 2020 |
| VITAS: A multi-purpose simulation code for the solution of neutron transport problems based on variational nodal methods T Zhang, W Xiao, H Yin, Q Sun, X Liu Annals of Nuclear Energy 178, 109335, 2022 | 27 | 2022 |
| An improved variational nodal method for the solution of the three-dimensional steady-state multi-group neutron transport equation T Zhang, H Wu, L Cao, Y Li Nuclear Engineering and Design 337, 419-427, 2018 | 26 | 2018 |
| Development and implementation of an integral variational nodal method to the hexagonal geometry nuclear reactors T Zhang, J Xiong, L Liu, Z Li, K Zhuang Annals of Nuclear Energy 131, 210-220, 2019 | 21 | 2019 |
| Variational nodal methods for neutron transport: 40 years in review T Zhang, Z Li Nuclear Engineering and Technology 54 (9), 3181-3204, 2022 | 19 | 2022 |
| Single-step Monte Carlo criticality algorithm Q Pan, N An, T Zhang, X Liu, Y Cai, L Wang, K Wang Computer Physics Communications 279, 108439, 2022 | 18 | 2022 |
| Lagrangian simulation of three-dimensional macro-scale melting based on enthalpy method J Xiong, Y Zhu, T Zhang, X Cheng Computers & Fluids 190, 168-177, 2019 | 16 | 2019 |
| Acceleration of 3D pin-by-pin calculations based on the heterogeneous variational nodal method T Zhang, H Wu, L Cao, Y Li Annals of Nuclear Energy 114, 165-174, 2018 | 16 | 2018 |
| Conceptual design and thermal-hydraulic analysis of a megawatt-level lead-bismuth cooling reactor for deep-sea exploration Q Yang, Q Sun, X Liu, H He, T Zhang, X Chai, Y Luo Progress in Nuclear Energy 145, 104125, 2022 | 14 | 2022 |
| Experimental study on transient heat transfer performance of high temperature heat pipe under temperature feedback heating mode for micro nuclear reactor applications J Deng, T Wang, X Liu, T Zhang, H He, X Chai Applied Thermal Engineering 230, 120826, 2023 | 12 | 2023 |
| Predictions of quench temperature and quench velocity in narrow rectangular channel of novel plate-type reactor W Xu, J Guo, X Liu, J Xiong, X Chai, T Zhang, X Cheng, W Zeng Annals of Nuclear Energy 131, 148-155, 2019 | 12 | 2019 |
| SP3-coupled global variance reduction method based on RMC code QQ Pan, TF Zhang, XJ Liu, H He, K Wang Nuclear Science and Techniques 32 (11), 122, 2021 | 11 | 2021 |
| Extended development of a Monte Carlo code OpenMC for fuel cycle simulation of molten salt reactor K Zhuang, T Li, Q Zhang, Q He, T Zhang Progress in Nuclear Energy 118, 103115, 2020 | 11 | 2020 |
| A comparison of three algorithms applied in thermal-hydraulics and neutronics codes coupling for lbe-cooled fast reactor D Yang, X Liu, T Zhang, X Cheng Annals of Nuclear Energy 149, 107789, 2020 | 10 | 2020 |
| Conceptual design of an innovative reduced moderation thorium‐fueled small modular reactor with heavy‐water coolant T Zhang, J Xiong, X Liu, X Chai, W Li, X Cheng International Journal of Energy Research 43 (14), 8286-8298, 2019 | 10 | 2019 |
| Multi-physics coupled simulation on steady-state and transients of heat pipe cooled reactor system T Li, J Xiong, T Zhang, X Chai, X Liu Annals of Nuclear Energy 187, 109774, 2023 | 9 | 2023 |
