代表性论文专著
Book Chapters
Nuclear Physics Deterministic Code, Nuclear Power Plant Design and Analysis Codes Development, Validation, and Application for Science and Technology, Elsevier, 2019.
Supercritical Water Reactors, Nuclear Power Reactor Designs- From History to Advances, Elsevier, 2024.
Lead Fast Reactors, Nuclear Power Reactor Designs- From History to Advances, Elsevier, 2024.
Selected Publications
-Zhang T, Sun Q, Xiao W, Luo C, Liu X*. A review on emerging mixed-spectrum nuclear reactors for safety and sustainability of nuclear energy systems. Renewable and Sustainable Energy Reviews. 2024 Sep 1;202:114666.
-Xiao W, Liu X, Zu J, Chai X, He H, Zhang T*. Operator inference driven data assimilation for high fidelity neutron transport. Computer Methods in Applied Mechanics and Engineering. 2024 Oct 1;430:117214.
-Sun Q, Liu X, Chai X, He H, Zhang T*. A discrete-ordinates variational nodal method for heterogeneous neutron Boltzmann transport problems. Computers & Mathematics with Applications. 2024 Sep 15;170:142-60.
- Yin H, Liu X, Zhang T*. An efficient parallel algorithm of variational nodal method for heterogeneous neutron transport problems. Nuclear Science and Techniques. 2024 Apr;35(4):69.
- Li X, Liu X, Chai X, He H, Zhang B, Zhang T*. Multi-physics coupling simulation of small mobile nuclear reactor with finite element-based models. Computer Physics Communications. 2023 Aug 25:108900.
- Zhang J, Li T, Shen Z, Li X, Xiong J, Chai X, Liu X, Zhang T*. Investigations of multiphysics models on a megawatt-level heat pipe nuclear reactor based on high-fidelity approaches. Nuclear Science and Engineering. 2023 Aug 5:1-25.
- Sun Q, Xiao W, Li X, Yin H, Zhang T*, Liu X. A variational nodal formulation for multi-dimensional unstructured neutron diffusion problems. Nuclear Engineering and Technology. 2023 Feb 20.
- Xiao W, Yin H, Liu X, He H, Zhang T*. On the transient models of the VITAS code: applications to the C5G7-TD pin-resolved benchmark problem. Nuclear Science and Techniques. 2023 Feb;34(2):20.
- Zhang T, Xiao W, Yin H, Sun Q, Liu X*. VITAS: A multi-purpose simulation code for the solution of neutron transport problems based on variational nodal methods. Annals of Nuclear Energy. 2022 July 178:109335.
- Xiao W, Sun Q, Liu X, He H, He D, Pan Q, Zhang T*. Application of stiffness confinement method within variational nodal method for solving time-dependent neutron transport equation. Computer Physics Communications. 2022 Jun 8:108450.
- Zhang T*, Li Z*. Variational nodal methods for neutron transport: 40 years in review. Nuclear Engineering and Technology. 2022 Apr 27.
- Yin H, Zhang T*, He D, Liu X*. A quasi-transport integral variational nodal method for homogeneous nodes based on the 2D/1D method. Computer Physics Communications. 2022 Jan 14:108290.
- Xiao W, Li X, Li P, Zhang T*, Liu X. High-fidelity multi-physics coupling study on advanced heat pipe reactor. Computer Physics Communications. 2022 Jan 1;270:108152.
- Zhang T, Xiong J*, Liu L, Li Z, Zhuang K. Development and implementation of an integral variational nodal method to the hexagonal geometry nuclear reactors. Annals of Nuclear Energy. 2019 Sep 1;131:210-20.
- Zhang T*, Xiong J, Liu X, Chai X, Li W, Cheng X. Conceptual design of an innovative reduced moderation thorium‐fueled small modular reactor with heavy‐water coolant. International Journal of Energy Research. 2019 Nov;43(14):8286-98.
- Zhang T*, Wu H, Cao L, Li Y. An improved variational nodal method for the solution of the three-dimensional steady-state multi-group neutron transport equation. Nuclear Engineering and Design. 2018 Oct 1;337:419-27.
- Zhang T*, Liu X, Xiong J, Cheng X. Comparisons of reduced moderation small modular reactors with heavy water coolant. Frontiers in Energy Research. 2020:27.
- Zhang T*, Yin H, Li X, She D, Pan Q, He D, Liu X. Studies on calculation models of ASTRA critical facility benchmark using OpenMC. Annals of Nuclear Energy. 2021 Aug 1;158:108291.
- Zhang T, Xiong J*. A hybrid acceleration method to pin-by-pin calculations using the heterogeneous variational nodal method. Annals of Nuclear Energy. 2019 Oct 1;132:723-33.
- Zhang T*, Wu H, Cao L, Li Y. Acceleration of 3D pin-by-pin calculations based on the heterogeneous variational nodal method. Annals of Nuclear Energy. 2018 Apr 1;114:165-74.
- Zhang T*, Lewis EE, Smith MA, Yang WS, Wang Y, Wu H. Acceleration of within group iteration for pin-by-pin calculations. Annals of Nuclear Energy. 2018 Feb 1;112:225-35.
- Zhang T*, Wang Y, Lewis EE, Smith MA, Yang WS, Wu H. A three-dimensional variational nodal method for pin-resolved neutron transport analysis of pressurized water reactors. Nuclear Science and Engineering. 2017 Nov 2;188(2):160-74.
- Zhang T*, Lewis EE, Smith MA, Yang WS, Wu H. A variational nodal approach to 2D/1D pin resolved neutron transport for pressurized water reactors. Nuclear Science and Engineering. 2017 May 4;186(2):120-33.
- Zhang T, Wu H, Zheng Y*, Cao L, Li Y. A 3D transport-based core analysis code for research reactors with unstructured geometry. Nuclear Engineering and Design. 2013 Dec 1;265:599-610.