Nuclear Physics Deterministic Code, Nuclear Power Plant Design and Analysis Codes Development, Validation, and Application for Science and Technology, Elsevier, 2019.
. Tengfei Zhang, Jinbiao Xiong, Xiaojing Liu, et al. Conceptual design of an innovative reduced moderation thorium‐fueled small modular reactor with heavy‐water coolant [J]. International Journal of Energy Research. 2020. 43: 8286~8298.
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. Tengfei Zhang, Jinbiao Xiong. A Hybrid Acceleration Method to Pin-by-Pin Calculations using the Heterogeneous Variational Nodal Method [J]. Annals of Nuclear Energy, 2019. 132: 723~733.
. Tengfei Zhang, Jinbiao Xiong, Zhipeng Li, Kun Zhuang. Development and implementation of an integral variational nodal method to the hexagonal geometry nuclear reactors [J]. Annals of Nuclear Energy, 2019. 131: 210-220.
. Tengfei Zhang, Hongchun Wu, Liangzhi Cao, Yunzhao Li. An improved variational nodal method for the solution of the three dimensional steady-state multi-group neutron transport equation [J], Nuclear Engineering and Design, 2018. 337:419~427.
. Tengfei Zhang, Hongchun Wu, Liangzhi Cao, Yunzhao Li. Acceleration of 3D Pin-by-Pin Calculations Based on the Heterogeneous Variational Nodal Method [J], Annals of Nuclear Energy, 2018. 114:165~174.
. Tengfei Zhang, E. E. Lewis, M. A. Smith, et al. Acceleration of within group iteration for pin-by-pin calculations [J]. Annals of Nuclear Energy, 2018, 112:225~235.
. Tengfei Zhang, Yongping Wang, E. E. Lewis, et al. A Three-Dimensional Variational Nodal Method for Pin-Resolved Neutron Transport Analysis of Pressurized Water Reactors [J]. Nuclear Science and Engineering, 2017, 188(2): 160~174.
. Tengfei Zhang, E. E. Lewis, M. A. Smith, et al. A variational nodal approach to 2D/1D pin resolved neutron transport for pressurized water reactors[J]. Nuclear Science and Engineering, 2017, 186:120-133.
. Tengfei Zhang, Hongchun Wu, Youqi Zheng, et al. A 3D transport-based core analysis code for research reactors with unstructured geometry[J]. Nuclear Engineering and Design, 2013, 265: 599~610.
. Dongmei Yang, Xiaojing Liu, Tengfei Zhang, et al. A comparison of three algorithms applied in thermal-hydraulics and neutronics codes coupling for lbe-cooled fast reactor [J], Annals of Nuclear Energy, 2020, 149.
. Xiaojing Liu, Ting Yang, Xiang Chai, Jinbiao Xiong, Tengfei Zhang. Preliminary safety analysis for the SCWR-FQT facility [J]. International Journal of Energy Research, 2019:1-10.
. Jinbiao Xiong, Zenghui Wu, Xiang Chen, Tengfei Zhang. Experimental and analytical study on heat dissipation mechanisms during spent fuel unloading in sodium fast reactor[J]. Annals of Nuclear Energy, 2020, 136: 107010.
. Kun Zhuang, Ting Li, Qian Zhang, Qinghua He, Tengfei Zhang. Extended development of a Monte Carlo code OpenMC for fuel cycle simulation of molten salt reactor [J]. Progress in Nuclear Energy, 2020, 118.
. Jinbiao Xiong, Yingzi Zhu, Tengfei Zhang, et al. Lagrangian simulation of three-dimensional macro-scale melting based on enthalpy method[J]. Computers and Fluids, 2019. 168-177.
. Yongping Wang, Tengfei Zhang, E. E. Lewis, et al. Three-Dimensional Variational Nodal Method Parallelization for Pin Resolved Neutron Transport Calculations [J]. Progress in Nuclear Energy, 2019. 117.
. Yongping Wang, Yunzhao Li, Tengfei Zhang, et al. Generalized Partitioned Matrix Acceleration for Variational Nodal Diffusion Method[J]. Nuclear Science and Engineering, 2019. 193: 652-662.
. Xiaojing Liu, et al. Computational Fluid Dynamics and Subchannel Analysis of Lead–bismuth Eutectic-cooled Fuel Assembly Under Various Blockage Conditions[J]. Applied Thermal Engineering, 2020. 114419.
. Wei Xu, et al. Predictions of Quench Temperature and Quench Velocity in Narrow Rectangular Channel of Novel Plate-type Reactor [J]. Annals of Nuclear Energy, 2019. 131:148~155.
. Shengzhe Li, Dongmei Yang, Tengfei Zhang, and Xiaojing Liu. A Combined Method for Predicting the Boron Deposited Mass and the CIPS Risk [J]. Science and Technology of Nuclear Installations, 2019.