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张滕飞
副教授
所在系所：核科学与工程学院 |
教育背景
2015.09 - 2016.09 美国阿贡国家实验室 核工程部 联培博士
2014.09 - 2015.08 美国普渡大学 核工系 联培博士
2011.09 - 2017.03 西安交通大学 核工程系 博士
2007.09 - 2011.07 西安交通大学 核科学与技术学院 本科工作经历
2022.01至今 上海交通大学核科学与工程学院 副教授
2017.06 - 2021.12 上海交通大学核科学与工程学院 讲师
出访及挂职经历
2018.12 德国卡尔斯鲁厄理工学院 访问学者
2015.09 - 2016.09 美国阿贡国家实验室核工程部 联培博士
2014.09 - 2015.08 美国普渡大学核工系 联培博士
研究方向
核反应堆物理
中子学计算软件开发
基于变分原理/伽辽金法的中子输运算法
基于多物理场耦合技术的先进堆分析及应用
中子学计算软件开发
基于变分原理/伽辽金法的中子输运算法
基于多物理场耦合技术的先进堆分析及应用
（常年招收硕士、博士研究生）
科研项目
主持自然基金面上、青年、重点研发子任务等科研项目近30项。主要承担纵向课题：
ø 2022-2025 国家自然科学基金面上项目，基于复杂构型中子输运算法的小型核反应堆核-热-力耦合研究（12175138）ø 2022-2025 中核集团领创科研项目，热膨胀条件下固体微型反应堆的物理-热工耦合特性研究
ø 2020-2023 国家重点研发计划子课题，小型氦氙冷却移动式固体堆核热材多物理耦合技术（2020YFB1901900）
ø 2020-2023 国家自然科学基金联合基金重点项目，铅铋合金熔池热分层机理及对系统流动传热影响研究（U1967204），本单位课题负责人
ø 2020-2023 中核集团青年英才启明星项目，海洋核动力反应堆强共用性中子输运算法及核热耦合研究
ø 2019-2021 中国科协青年人才托举工程，先进中子输运算法及其在核热耦合中的应用研究（2019QNRC001）
ø 2019-2021 国家自然科学基金青年项目，核反应堆高分辨率高效率非均匀中子输运计算方法研究（11805122）
主要参与纵向课题
ø 2021-2024 国家自然科学基金联合基金重点项目，针对堆芯氧化腐蚀产物材料-热工-中子行为的多物理耦合机理（U20B2011），第二负责人
ø 2019-2022 国家自然科学基金青年项目，液滴撞击高温表面的关键换热现象及模型研究
ø 2014-2016 国家自然科学基金青年项目，核反应堆全堆芯非均匀中子学分析的高精度高效率计算方法研究
代表性论文专著
书籍章节:
Nuclear Physics Deterministic Code, Nuclear Power Plant Design and Analysis Codes Development, Validation, and Application for Science and Technology, Elsevier, 2019.Nuclear Physics Deterministic Code, Nuclear Power Plant Design and Analysis Codes Development, Validation, and Application for Science and Technology, Elsevier, 2019.
- 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 Physics Deterministic Code, Nuclear Power Plant Design and Analysis Codes Development, Validation, and Application for Science and Technology, Elsevier, 2019.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, 2022 (to appear).
Lead Fast Reactors, Nuclear Power Reactor Designs- From History to Advances, Elsevier, 2022 (to appear).
发表SCI论文60余篇。代表性论文：
- 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.
教学工作
工程与社会 授课对象：本科生 课时：48
核反应堆物理 授课对象：本科生 课时：24
高等核反应堆物理 授课对象：研究生 课时：48
核反应堆物理 授课对象：本科生 课时：24
高等核反应堆物理 授课对象：研究生 课时：48
软件版权登记及专利
授权发明专利及软件著作权30余项
自主开发程序：
1. VITAS - 通用型中子输运求解器，应用对象：商用热谱和快谱堆/微型堆两步法计算、压水堆一步法高保真计算；
2. MORPHY - 非结构网格多功能多物理耦合分析软件，应用对象：实验堆、铅基堆；
3. MPCH - 高保真热管堆核热力耦合分析平台，应用对象：热管微堆；
4. FEMAS - 氦氙堆有限元多物理场模拟平台，应用对象：氦氙微堆。
自主开发程序：
1. VITAS - 通用型中子输运求解器，应用对象：商用热谱和快谱堆/微型堆两步法计算、压水堆一步法高保真计算；
2. MORPHY - 非结构网格多功能多物理耦合分析软件，应用对象：实验堆、铅基堆；
3. MPCH - 高保真热管堆核热力耦合分析平台，应用对象：热管微堆；
4. FEMAS - 氦氙堆有限元多物理场模拟平台，应用对象：氦氙微堆。
学术兼职
中国核学会 核物理分会 反应堆物理与核材料专委会，委员
中国核学会 计算物理分会 反应堆数值计算与粒子输运专业委员会，委员
2019 第十一届全国新堆与研究堆学术会议，组委会委员
2018 OECD/NEA CFD4NRS Workshop, Local Organizing Committee Member
2017 国防科技工业核动力技术创新中心暨核反应堆系统设计技术重点实验室年会，技术报告主席
2016 Annual Meeting of American Nuclear Society, Technical Session Chair
2014 22nd International Conference on Nuclear Engineering, Technical Session Chair
Invited Talks
2021 “先进核反应堆多物理场耦合算法及应用研究”，第二届NECP核创讲坛，西安交通大学.
2020 “确定论非均匀中子输运算法综述”，第十八届反应堆数值计算与粒子输运学术会议（反应堆物理年会）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.
中国核学会 计算物理分会 反应堆数值计算与粒子输运专业委员会，委员
第19届全国反应堆物理年会，组委会副主席
Frontiers in Energy Research，Guest Associate Editor
International Journal of Advanced Nuclear Reactor Design and Technology，Youth Editorial Board Member2019 第十一届全国新堆与研究堆学术会议，组委会委员
2018 OECD/NEA CFD4NRS Workshop, Local Organizing Committee Member
2017 国防科技工业核动力技术创新中心暨核反应堆系统设计技术重点实验室年会，技术报告主席
2016 Annual Meeting of American Nuclear Society, Technical Session Chair
2014 22nd International Conference on Nuclear Engineering, Technical Session Chair
Invited Talks
2021 “先进核反应堆多物理场耦合算法及应用研究”，第二届NECP核创讲坛，西安交通大学.
2020 “确定论非均匀中子输运算法综述”，第十八届反应堆数值计算与粒子输运学术会议（反应堆物理年会）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.
荣誉奖励
2023 上海市青年科技启明星
2022 杨福家核科技青年人才奖
2020 中核集团青年英才启明星
2020 聘期考核优秀奖
2019 中国科协青年人才托举工程
2019 陕西省优秀博士论文奖
2022 杨福家核科技青年人才奖
2020 中核集团青年英才启明星
2020 聘期考核优秀奖
2019 中国科协青年人才托举工程
2019 陕西省优秀博士论文奖
地址：中国·上海市闵行区东川路800号 200240
网址：：http://nsse.sjtu.edu.cn
电话：021-34205182 传真：021-34205182
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