? 2011.09 - 2017.03       西安交通大學(xué)                    核工程系                      博士
? 2015.09 - 2016.09       美國阿貢國家實驗室          核工程部                      聯(lián)培博士
? 2014.09 - 2015.08       美國普渡大學(xué)                    核工系                         聯(lián)培博士
? 2007.09 - 2011.07       西安交通大學(xué)                    核科學(xué)與技術(shù)學(xué)院        本科

2021.12至今   上海交通大學(xué)  機械與動力工程學(xué)院 核科學(xué)與工程學(xué)院       副教授
2017.06-2021.12  上海交通大學(xué)  機械與動力工程學(xué)院 核科學(xué)與工程學(xué)院       講師

? 核反應(yīng)堆變分中子輸運計算方法
? 先進核反應(yīng)堆多物理場耦合
? 物理-數(shù)據(jù)驅(qū)動的中子輸運降階模擬方法
? 核反應(yīng)堆堆芯探測器優(yōu)化及狀態(tài)監(jiān)測
? 中子噪聲分析及反演

中國核學(xué)會船用核動力分會，理事
中國核學(xué)會 核物理分會 反應(yīng)堆物理與核材料專委會，委員
中國核學(xué)會 計算物理分會 反應(yīng)堆數(shù)值計算與粒子輸運專委會，委員
第19屆全國反應(yīng)堆數(shù)值計算與粒子輸運會議，組委會副主席
Frontiers in Energy Research，Guest Associate Editor
International Journal of Advanced Nuclear Reactor Design and Technology，Youth Editorial Board Member
2019 第十一屆全國新堆與研究堆學(xué)術(shù)會議，組委會委員
2018 OECD/NEA CFD4NRS Workshop, Local Organizing Committee Member

Invited Talks

2025 “針對時-空中子輸運方程的算子推斷方法及數(shù)據(jù)同化研究”，第四屆全國核物理及和數(shù)據(jù)中的機器學(xué)習(xí)應(yīng)用研討會.

2025 “針對時-空中子輸運方程的算子推斷方法及應(yīng)用研究”，核反應(yīng)堆技術(shù)全國重點實驗室2025年學(xué)術(shù)年會.

2025 “INSL先進變分節(jié)塊法研究進展”，中廣核研究院有限公司.

2025 “先進核反應(yīng)堆堆芯多物理場耦合”，中國科學(xué)院核能安全技術(shù)研究所.

2025 “針對時-空中子輸運方程的算子推斷方法及應(yīng)用研究 ”，輸運方程的計算與應(yīng)用研討會，上海交通大學(xué).

2025 “先進反應(yīng)堆堆芯多物理場耦合”，NECP核創(chuàng)講壇，西安交通大學(xué).

2025 “針對核反應(yīng)堆堆芯中子輸運問題的變分節(jié)塊法”，重慶大學(xué).

2025 “先進反應(yīng)堆堆芯多物理場耦合”，青年創(chuàng)新促進會學(xué)術(shù)沙龍，中科院上海應(yīng)用物理所.

2024 “先進變分節(jié)塊法研究進展”，全國新堆與研究堆第一屆學(xué)術(shù)年會.
2024 “基于變分法的核反應(yīng)堆確定論中子輸運計算方法”，北京應(yīng)用物理與計算數(shù)學(xué)研究所第六屆學(xué)術(shù)年會.
2024 “Current research status of LFRs at INSL”， 34th GIF LFR Prov. SSC Meeting.
2024 “基于變分法的先進確定論中子輸運計算方法”，核反應(yīng)堆技術(shù)全國重點實驗室2024年學(xué)術(shù)年會.
2023  “面向精細化復(fù)雜中子輸運問題的變分節(jié)塊法”，中核集團第三屆核工業(yè)青年科技論壇.
2023  “新質(zhì)堆核熱力多物理耦合技術(shù)研究”，新質(zhì)堆關(guān)鍵物理技術(shù)研討會，中國核動力研究設(shè)計院.
2021 “先進核反應(yīng)堆多物理場耦合算法及應(yīng)用研究”，第二屆NECP核創(chuàng)講壇，西安交通大學(xué).
2020 “確定論非均勻中子輸運算法綜述”，第十八屆反應(yīng)堆數(shù)值計算與粒子輸運學(xué)術(shù)會議（反應(yīng)堆物理年會）Workshop，西安.
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”, Karlsrule Institute of Technology, Germany.

主要承擔(dān)縱向課題

? 2026-2028 國家自然科學(xué)基金青年科學(xué)基金項目（B類），核反應(yīng)堆中子輸運方法及應(yīng)用

? 2025-2028 中核集團領(lǐng)創(chuàng)科研項目，高分辨率變分節(jié)塊法及降階模擬方法研究

? 2022-2025 國家自然科學(xué)基金面上項目，基于復(fù)雜構(gòu)型中子輸運算法的小型核反應(yīng)堆核-熱-力耦合研究
? 2022-2025 中核集團領(lǐng)創(chuàng)科研項目，熱膨脹條件下固體微型反應(yīng)堆的物理-熱工耦合特性研究
? 2020-2023 國家重點研發(fā)計劃子課題，小型氦氙冷卻移動式固體堆核熱材多物理耦合技術(shù)
? 2020-2023 中核集團青年英才啟明星項目，海洋核動力反應(yīng)堆強共用性中子輸運算法及核熱耦合研究
? 2019-2021 中國科協(xié)青年人才托舉工程，先進中子輸運算法及其在核熱耦合中的應(yīng)用研究
? 2019-2021 國家自然科學(xué)基金青年科學(xué)基金項目，核反應(yīng)堆高分辨率高效率非均勻中子輸運計算方法研究

主要參與縱向課題
? 2021-2024 國家自然科學(xué)基金聯(lián)合基金重點項目，針對堆芯氧化腐蝕產(chǎn)物材料-熱工-中子行為的多物理耦合機理，第二負責(zé)人
? 2019-2022 國家自然科學(xué)基金青年項目，液滴撞擊高溫表面的關(guān)鍵換熱現(xiàn)象及模型研究
? 2014-2016 國家自然科學(xué)基金青年項目，核反應(yīng)堆全堆芯非均勻中子學(xué)分析的高精度高效率計算方法研究
（本課題組常年招收碩士、博士研究生）

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*, 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.

授權(quán)發(fā)明專利及軟件著作權(quán)50余項
自主開發(fā)程序：
1. VITAS - 通用型中子輸運求解器，應(yīng)用對象：商用熱譜和快譜堆/微型堆兩步法、一步法高保真計算；
2. MORPHY - 非結(jié)構(gòu)網(wǎng)格多功能多物理耦合分析軟件，應(yīng)用對象：實驗堆、鉛基堆、C2反應(yīng)堆；
3. MPCH - 高保真熱管堆核熱力耦合分析平臺，應(yīng)用對象：熱管微堆；
4. FEMAS - 氦氙堆有限元多物理場模擬平臺，應(yīng)用對象：氦氙微堆。