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Tengfei Zhang
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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
422017
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
372020
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
372017
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
342022
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
302020
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
262018
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
242022
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
212019
Variational nodal methods for neutron transport: 40 years in review
T Zhang, Z Li
Nuclear Engineering and Technology 54 (9), 3181-3204, 2022
162022
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
162019
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
162018
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
152022
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
142022
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
122019
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
102023
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
102021
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
102020
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
102019
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
92023
Preliminary lightweight core design analysis of a micro‐transportable gas‐cooled thermal reactor
C Guan, X Chai, T Zhang, X Liu
International Journal of Energy Research 46 (12), 17416-17428, 2022
92022
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