Ph.D. Nuclear Engineering, Xi'an Jiaotong University, China Sep/11 ~ 03/17
Guest Graduate N.E. Division, Argonne National Laboratory Aug/15 ~ Sep/16
Visiting Scholar School of nuclear engineering, Purdue University Sep/14 ~ Aug/15
B.E. Nuclear Engineering, Xi'an Jiaotong University, China Sep/07 ~ 07/11

Professor, School of Mechanical Engineering, Shanghai Jiao Tong University June/2026~Present
Associate Professor, School of Mechanical Engineering, Shanghai Jiao Tong University Dec/2021~June/2026
Assistant Professor, School of Mechanical Engineering, Shanghai Jiao Tong University Nov/2017~Dec/2021

Visiting Scholar Karlsruher Institut für Technologie, Germany Dec/18
Guest Graduate N.E. Division, Argonne National Laboratory Aug/15 ~ Sep/16
Visiting Scholar School of nuclear engineering, Purdue University Sep/14 ~ Aug/15

Advanced numerical algorithms for neutron transport
Multiphysics coupling of nuclear reactor cores
Model-data-driven reduced-order modelling and data assimilation methods
Neutron noise analysis and anomaly diagnosis methods for power reactor cores

2027–2031 Key Program of the National Natural Science Foundation of China, Model-Data-Driven Signal-Noise Integrated Monitoring Methods for Nuclear Reactor Cores
2026–2028 Young Scientists Fund (Category B) of the National Natural Science Foundation of China, Neutron Transport Methods and Applications for Nuclear Reactors
2022–2025 General Program of the National Natural Science Foundation of China, Research on Neutronics-Thermal-Mechanical Coupling of Small Nuclear Reactors Based on Neutron Transport Algorithms for Complex Configurations
2019–2021 Young Scientists Fund of the National Natural Science Foundation of China, Research on High-Resolution and High-Efficiency Heterogeneous Neutron Transport Computation Methods for Nuclear Reactors
2020–2023 Sub-project of the National Key R&D Program of China, Neutronics-Thermal-Material Multiphysics Coupling Technology for Small Helium-Xenon-Cooled Mobile Solid Reactors
2019–2021 Young Talent Support Project of the China Association for Science and Technology, Advanced Neutron Transport Algorithms and Their Applications in Neutronics-Thermal Coupling
2025–2028 CNNC Leading Innovation Research Project, Research on High-Resolution Variational Nodal Methods and Reduced-Order Simulation Methods
2022–2025 CNNC Leading Innovation Research Project, Research on Neutronics-Thermal-Hydraulic Coupling Characteristics of Solid Microreactors under Thermal Expansion Conditions
2020–2023 CNNC Young Talent “Morning Star” Program, Research on Highly Universal Neutron Transport Algorithms and Neutronics-Thermal Coupling for Marine Nuclear Power Reactors

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
-Luo C, Wang S, Liu X, Chai X, He H, Zhang T*. Hyper-reduction-based data assimilation for nuclear reactor core flux monitoring under complex measurement scenarios: implementation and adaptive tuning. Reliability Engineering & System Safety. 2026 Jul 7:113126.
-Zhang T, Xiao W, Wang S, Zu J, Liu X*. Coupling-informed operator inference: structure-preserving reduced-order modeling for multi-physics equations. Journal of Computational Physics. 2026 Jun 18:115145.
-Zhang T*, Shen S, Hu L, Liu X. Multi-physics coupling rapid prediction method and autonomous control method for heat pipe nuclear reactors. Annals of Nuclear Energy. 2026 Feb 1;227:111927.
-Luo C, Wang S, Liu X, Chai X, He H, Zhang T*. Sensor Placement Optimization and Online Power Reconstruction in Nuclear Reactors via Hyper-reduction. IEEE Sensors Journal. 2025 Sep 29.
-Zhang J, Chen Y, Liu X, Chai X, He H, Xiong J, Zhang T*. Optimizing thermal stress distribution in heat-pipe-cooled microreactors using multi-physics data-driven methods. Energy. 2025 May 15;323:135679.
-Yin H, Liu X, Chai X, He H, Wang L, Zhang B, Zhang T*. A Numerical Stabilization Model for the Half-Boundary Method in Solving Heat Conduction Problems. Annals of Nuclear Energy. 2025; 224:111734.
-Zhang C, Yin H, Liu Y, He H, Liu X, Zhang T*, Wang S. High-Resolution Multiphysics Analysis of CRUD Effects in Reactor Assemblies. PRX Energy. 2025 Sep 1;4(3):033016.
-Li X, Sun Q, Liu X, Chai X, He H, Zhang T*. A comparative study of high and low order neutronics calculation models in microreactors. Annals of Nuclear Energy. 2025 Jun 1;215:111205.
-Luo C, Yang M, Zhu Q, Zhang C, Liu X, Zhang T*. Neutronics analysis of a research reactor using a two-step method with the superhomogenization method. Annals of Nuclear Energy. 2025 Feb 1;211:110912.
-Sun Q, Liu X, Chai X, He H, Wang L, Zhang B, Zhang T. Hybrid discontinuous Galerkin method for the hyperbolic linear Boltzmann transport equation for multiscale problems. Physical Review E. 2024 Dec;110(6):065301.
-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.
-Zhang T, Yang M, Luo C, et al. Multi-physics coupled analyzes of research nuclear reactors based on steady-state and kinetics models. Annals of Nuclear Energy, 2024, 196: 110231.
-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.
-Luo C, Li Z, Yin H, Wang L, Zhang B, Liu X, Chai X, He H, Zhang T*. Application of full-core three-dimensional multi-physics calculation to the EBR-II SHRT-45R benchmark. Annals of Nuclear Energy. 2024 Dec 1;208:110786.
- 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.

Nuclear Reactor Design, Graduate Course
Nuclear Reactor Physics, Undergraduate Course

Over 70 authorized invention patents and software copyrights.

Independently Developed Codes:
VITAS – General-purpose neutron transport solver. Applications: two-step and one-step high-fidelity calculations for commercial thermal-spectrum and fast-spectrum reactors/microreactors.
MORPHY – Unstructured-mesh multifunctional multiphysics coupling analysis software. Applications: experimental reactors, lead-based reactors, and SCO2 reactors.
MPCH – High-fidelity neutronics–thermal–mechanical coupling analysis platform for heat pipe reactors. Applications: heat pipe microreactors.
FEMAS – Finite element multiphysics simulation platform for helium–xenon reactors. Applications: helium–xenon microreactors.

China Nuclear Society, Marine Nuclear Power Branch, Council Member
China Nuclear Society, Nuclear Physics Branch, Reactor Physics and Nuclear Materials Committee, Member
China Nuclear Society, Computational Physics Branch, Reactor Numerical Computation and Particle Transport Committee, Member
The 19th National Conference on Reactor Numerical Computation and Particle Transport, Vice Chair of the Organizing Committee
International Journal of Advanced Nuclear Reactor Design and Technology, Youth Editorial Board Member
Nuclear Power Engineering, Youth Editorial Board Member
High Power Laser and Particle Beams, Youth Editorial Board Member
2019 The 11th National Conference on New Reactors and Research Reactors, Organizing Committee Member
2018 OECD/NEA CFD4NRS Workshop, Local Organizing Committee Member

Invited Talks
2025 “Operator Inference Methods and Data Assimilation for Space-Time Neutron Transport Equations,” The 4th National Symposium on Machine Learning Applications in Nuclear Physics and Nuclear Data.
2025 “Operator Inference Methods and Applications for Space-Time Neutron Transport Equations,” 2025 Annual Academic Conference of the National Key Laboratory of Nuclear Reactor Technology.
2025 “Research Progress on the INSL Advanced Variational Nodal Method,” CGN Research Institute Co., Ltd.
2025 “Multiphysics Coupling of Advanced Nuclear Reactor Cores,” Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences.
2025 “Operator Inference Methods and Applications for Space-Time Neutron Transport Equations,” Workshop on Computation and Applications of Transport Equations, Shanghai Jiao Tong University.
2025 “Multiphysics Coupling of Advanced Reactor Cores,” NECP Nuclear Innovation Forum, Xi’an Jiaotong University.
2025 “Variational Nodal Method for Neutron Transport Problems in Nuclear Reactor Cores,” Chongqing University.
2025 “Multiphysics Coupling of Advanced Reactor Cores,” Academic Salon of the Youth Innovation Promotion Association, Shanghai Institute of Applied Physics, Chinese Academy of Sciences.
2024 “Research Progress on the Advanced Variational Nodal Method,” The 1st National Annual Academic Conference on New Reactors and Research Reactors.
2024 “Variational-Method-Based Deterministic Neutron Transport Computation Methods for Nuclear Reactors,” The 6th Annual Academic Conference of the Beijing Institute of Applied Physics and Computational Mathematics.
2024 “Current research status of LFRs at INSL,” 34th GIF LFR Prov. SSC Meeting.
2024 “Advanced Deterministic Neutron Transport Computation Methods Based on Variational Methods,” 2024 Annual Academic Conference of the National Key Laboratory of Nuclear Reactor Technology.
2023 “Variational Nodal Method for Refined and Complex Neutron Transport Problems,” The 3rd Nuclear Industry Youth Science and Technology Forum, China National Nuclear Corporation (CNNC).
2023 “Research on Neutronics-Thermal-Mechanical Multiphysics Coupling Technology for New-Quality Reactors,” Symposium on Key Physics Technologies for New-Quality Reactors, Nuclear Power Institute of China.
2021 “Research on Multiphysics Coupling Algorithms and Applications for Advanced Nuclear Reactors,” The 2nd NECP Nuclear Innovation Forum, Xi’an Jiaotong University.
2020 “Review of Deterministic Heterogeneous Neutron Transport Algorithms,” Workshop of the 18th National Conference on Reactor Numerical Computation and Particle Transport (Annual Conference on Reactor Physics), Xi’an.
2019 “Variational Nodal Approaches to Solving Neutron Transport Problems”, Kyushu University, Japan.
2018 “GPM Acceleration to the Diffusion Heterogeneous Variational Nodal Method”, Tokyo University, Japan.
2018 “A Pin-resolved Variational Nodal Method for the Modelling of Nuclear Reactor Cores”, Karlsruhe Institute of Technology, Germany.

Research
2025 Recipient, Young Scientists Fund (Category B), National Natural Science Foundation of China
2023 Shanghai Youth Science and Technology Rising Star
2020 CNNC Young Talent Rising Star
2019 Young Talent Support Project, China Association for Science and Technology (CAST)
2025 First Prize, Technology Invention Award, Ministry of Education (ranked 6th)
2024 First Prize, Technology Invention Award, Chinese Nuclear Society (ranked 2nd)
2023 First Prize, Electric Power Innovation Technology Achievement Award (ranked 3rd)
2022 Yang Fujia Nuclear Science and Technology Young Talent Award
2019 Shaanxi Province Outstanding Doctoral Dissertation Award

Teaching and Education
2024 Third Prize, Teaching and Education Award, Shanghai Jiao Tong University
2023 Second Prize, Young Faculty Teaching Competition, Shanghai Jiao Tong University
2021 Third Prize, Young Faculty Teaching Competition, School of Mechanical Engineering
2021 Shanghai Nuclear Engineering Research and Design Institute Teaching Award
2020 Supervising Instructor, Third Prize, University–Industry Collaborative Graduation Design
2020 Faculty Advisor, Meritorious Winner (M Award), Mathematical Contest in Modeling (MCM)
2017 Faculty Advisor, Champion, “Zhichuang Cup” Freshman Mechanical Competition, Shanghai Jiao Tong University
2017 Outstanding Class Advisor, Shanghai Jiao Tong University