基本信息

吴文斌，男，副教授、博士生导师，中山大学中法核工程与技术学院

电子邮箱：wuwb28@mail.sysu.edu.cn

Personal Data

Wenbin Wu, Associate Professor, Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-sen University

Email：wuwb28@mail.sysu.edu.cn

 

学术寄语

本团队长期招收博士后、博士生、硕士生，欢迎核工程、应用数学、计算机等专业学子申请、报考。学有余力且感兴趣的本科生，请联系我加入研究团队。

欢迎相关领域的科研合作。

Academic messages

Openings of postdoctoral researchers, Ph.D. students, and master's students are available. Students majoring in nuclear engineering, applied mathematics, computer science, etc., are welcome to apply. Undergraduate students interested in my topics, please feel free to contact me.

Research cooperation in related fields is appreciated.

 

教育经历

2005.08-2009.07，清华大学工程物理系，核能科学与工程专业，工学学士；

2009.09-2014.07，清华大学工程物理系，核科学与技术专业，工学博士。

Education Background

2005.08-2009.07, Bachelor's Degree of Nuclear Science and Technology, Department of Engineering Physics, Tsinghua University, Beijing

2009.09-2014.07, PhD Degree of Nuclear Science and Technology, Department of Engineering Physics, Tsinghua University, Beijing

  

工作经历

2014.07-2016.12，XXX设计院，工程师；

2016.12-2017.12，XXX设计院，高级工程师；

2017.12-2018.12，美国麻省理工学院核科学与工程系，公派留学；

2018.12-2020.07，XXX设计院，高级工程师；

2020.07-至今，中山大学中法核工程与技术学院，“百人计划”引进副教授.

Professional Experience

2014.07-2016.12， Nuclear Engineer；

2016.12-2017.12， Senior Nuclear Engineer；

2017.12-2018.12， Massachusetts Institute of Technology， Postdoctoral Researcher；

2018.12-2020.07， Senior Nuclear Engineer；

2020.07-Now， Sun Yat-sen University， Associate Professor.

  

讲授课程

反应堆物理, 中子输运计算程序, 核电厂运行, Linux系统和开源工具计算工具, C/C++编程, Matlab程序开发

Classes

Reactor Physics, Neutron transport code, Operation of nuclear power plant, Linux system and open-source tools, C/C++ programming, Matlab programming

  

主持的科研项目

近三年主持国家级、省部级、校企合作等科研项目7项，承担竞争性科研经费共计700余万元。 

三维特征线程序的角度并行和非方形栅格几何三维输运加速研究，2024年

 三维特征线程序的耦合封装和瞬态模块研究，2023年 

XXX堆芯精细化设计技术研究，2022年-2024年 

特征线程序输运模块旋转对称边界条件研究，2022年 

新型堆芯物理计算验证，2022年 

六角形几何中子输运特征线程序开发技术服务，2021年 

组件程序外部燃耗链读取功能开发，2020年 

基于三维特征线方法的弥散燃料与可燃毒物双重非均匀性分析方法研究，2019年-2021年 

基于逆波兰表示法的中子输运特征线法组合几何建模研究，2019年 

扩散有限差分方法的大规模并行计算研究，2015年-2016年 

基于一步法的全堆芯确定论中子学输运计算方法研究，2014年-2016年 

基于CPU+GPU并行的2D+1D三维全堆输运方法研究，2012年-2014年

Research Grants PI-ed

Implementation and acceleration of non-rectangular 3D MOC based on parallel computation, 2024

 Multi-physics coupling and transient analysis for 3D MOC, 2023 

Refined design of XXX reactor concept, 2022-2024 

Rotational boundary condition for 3D MOC, 2022 

Neutronics validation of a novel reactor design, 2022 

Development of MOC code for hexagonal geometry, 2021 

External depletion chain input for a lattice code, 2020 

Study on the double heterogeneity of dispersed fuel and poison based on 3D MOC, 2019-2021 

Study on Constructive Solid Geometry Modeling based on Reverse Polish Notation in Method of Characteristic for Neutron Transport, 2019 

Study on the finite difference solution of the neutron diffusion equation based on large-scale parallel computation, 2015-2016 

Study on the deterministic whole-core neutron transport based on the “one-step” method, 2014-2016 

Study on the 2D/1D coupling 3D neutron transport method by hybrid CPU and GPU parallelism, 2012-2014 

 

期刊审稿人

核动力工程, 核技术, Nuclear Science and Engineering, Annals of Nuclear Energy, Nuclear Engineering and Design, Progress in Nuclear Energy

Peer Reviewer

Nuclear Power Engineering, Nuclear Technologies, Nuclear Science and Engineering, Annals of Nuclear Energy, Nuclear Engineering and Design, Progress in Nuclear Energy

  

学术论文 (Publication list)

期刊文章 (Journal articles)

2021年-2023年 (From 2021 to 2023)

 [1]  Jingchao Zheng, Zhiqiang Wang, Zeyi Xie, Xingjie Peng, Chen Zhao, Wenbin Wu. Parallel Communication Optimization Based on Graph Partition for Hexagonal Neutron Transport Simulation Using MOC Method. Energies, 2023,16(6):2823.

 [2]  Yiming Zhong, Paul Norman, Wenbin Wu. A feasibility study of SMART reactor power performance optimizations-part 1: Steady-state and burn-up analysis. Frontiers in Energy Research, 2022,10.

 [3]  Yiming Zhong, Paul Norman, Wenbin Wu. A feasibility study of SMART reactor power performance optimizations-part 2: Reflector material selection. Frontiers in Energy Research, 2022,10.

 [4]  吴文斌, 王志强, 郑竞超, 谢择怿, 赵晨, 彭星杰. 六角形特征线方法及区域分解并行. 哈尔滨工程大学学报, 2023:1-5.

 [5]  Wenan PAN, Tianbo WANG, Zhibin WANG, Yonghao YANG, Hao WU, Geert VERDOOLAEGE, Zengchen YANG, Chunhua LIU, Wenping GUO, Bingli LI, Zijie LIU, Wenbin WU, Min XU. Integrated data analysis on the electron temperature profile of HL-2A with the Bayesian probability inference method. Plasma science & technology, 2022,24(5):55601.

 [6]  Helin Gong, Zhang Chen, Wenbin Wu, Xingjie Peng, Qing Li. Neutron noise calculation: A comparative study between SP3 theory and diffusion theory. Annals of Nuclear Energy, 2021,156:108184.

 

2010年-2020年 (From 2010 to 2020)

 [1]  Wenbin Wu, Guillaume Giudicelli, Kord Smith, Benoit Forget, Dong Yao, Yingrui Yu, Qi Luo. Improvements of the CMFD acceleration capability of OpenMOC. NUCLEAR ENGINEERING AND TECHNOLOGY, 2020,52(10):2162-2172.

 [2]  Wenbin Wu, Yingrui Yu, Qi Luo, Dong Yao, Qing Li, Xiaoming Chai. Matrix MOC: The method of characteristics in matrix form. Progress in Nuclear Energy, 2020,125:103378.

 [3]  Wenbin Wu, Yingrui Yu, Qi Luo, Dong Yao, Qing Li, Xiaoming Chai. Verification of the 3D capability of OpenMOC with the C5G7 3D extension benchmark. Annals of Nuclear Energy, 2020,140:107293.

 [4]  Wenbin Wu, Yingrui Yu, Qi Luo, Dong Yao, Qing Li, Xiaoming Chai. Calculation of higher eigenmodes of the forward and adjoint neutron diffusion equations using IRAM algorithm based on domain decomposition. Annals of Nuclear Energy, 2020,143:107463.

 [5]  Wenbin Wu, Yingrui Yu, Qing Li, Dong Yao, Qi Luo. Verification of the 2D/1D coupling 3D transport code TIGER with C5G7 benchmarks. International Journal of Advanced Nuclear Reactor Design and Technology, 2019,1:43-50.

 [6]  吴文斌, 于颖锐, 向宏志, 甯忠豪, 李庆. 基于大规模并行计算的三维多群中子扩散方程有限差分方法. 强激光与粒子束, 2017,29(08):141-146.

Wenbin Wu, Yingrui Yu, Hongzhi Xiang, Zhonghao Ning, Qing Li. Finite difference method for 3D multi-group neutron diffusion equation based on large-scale parallel computation. High Power Laser and Particle Beams, 2017,29(8):86001-86006. (in Chinese)

 [7]  吴文斌, 罗琦, 于颖锐, 李庆, 姚栋. 采用空间区域分解并行IRAM算法求解中子输运/扩散方程及其共轭方程的高阶谐波. 核动力工程, 2017,38(S2):1-6.

Wenbin Wu, Qi Luo, Yingrui Yu, Qing Li, Dong Yao. Calculation of Higher Eigenmodes of Neutron Transport/Diffusion Forward and Adjoint Equations Using IRAM Algorithm Based on Domain Decomposition. Hedongli Gongcheng/Nuclear Power Engineering, 2017,38:1-6. (in Chinese)

 [8]  吴文斌, 李庆, 王侃. 多区域耦合PGMRES算法用于加速区域分解并行矩阵MOC方法. 核动力工程, 2016,37(01):139-142.

Wenbin Wu, Qing Li, Kan Wang. Accelerating domain-decomposed parallel matrix MOC with multi-domain coupled PGMRES algorithm. Hedongli Gongcheng/Nuclear Power Engineering, 2016,37(1):139-142. (in Chinese)

 [9]  吴文斌, 李庆, 孙伟, 魏彦琴. 采用JFNK方法求解三维中子扩散方程. 核动力工程, 2015,36(S2):17-19.

Wenbin Wu, Qing Li, Wei Sun, Yanqin Wei. Solving 3-D neutron diffusion equation with JFNK algorithm. Hedongli Gongcheng/Nuclear Power Engineering, 2015,36:17-19. (in Chinese)

[10] 吴文斌, 李庆, 王侃. 基于大规模并行计算的2D/1D耦合三维全堆输运程序Tiger-3D. 核动力工程, 2014,35(S2):135-139.

Wenbin Wu, Qing Li, Kan Wang. Tiger-3D: 2D/1D coupled whole-core transport code based on large-scale parallel computation. Hedongli Gongcheng/Nuclear Power Engineering, 2014,35:135-139. (in Chinese)

[11] 吴文斌, 李庆, 王侃. 结合多群耦合GMRES的Wielandt迭代用于加速矩阵MOC收敛. 核动力工程, 2014,35(04):5-9.

Wenbin Wu, Qing Li, Kan Wang. Wielandt iteration combined with multi-group GMRES for accelerating matrix MOC convergence. Hedongli Gongcheng/Nuclear Power Engineering, 2014,35(4):5-9.

[12] 吴文斌, 李庆, 王侃. 基于模块化射线追踪的矩阵MOC方法(1)——理论研究. 核动力工程, 2014,35(03):129-133.

Wenbin Wu, Qing Li, Kan Wang. Matrix method of characteristics based on modular ray tracing (1) - theory. Hedongli Gongcheng/Nuclear Power Engineering, 2014,35(3):129-133. (in Chinese)

[13] 吴文斌, 李庆, 王侃. 基于模块化射线追踪的矩阵MOC方法(2)——数值验证. 核动力工程, 2014,35(03):134-137.

Wenbin Wu, Qing Li, Kan Wang. Matrix method of characteristics based on modular ray tracing (2) - numerical verification. Hedongli Gongcheng/Nuclear Power Engineering, 2014,35(3):134-137. (in Chinese)

[14] 吴文斌, 李庆, 王侃. 应用CMFD加速区域分解的并行MOC. 核动力工程, 2014,35(01):1-4.

Wenbin Wu, Qing Li, Kan Wang. Spatial domain-decomposed parallel MOC accelerated by CMFD. Hedongli Gongcheng/Nuclear Power Engineering, 2014,35(1):1-4. (in Chinese)

[15] 吴文斌, 李庆, 王侃. 基于HYPRE并行求解三维中子扩散方程. 原子能科学技术, 2013,47(S1):48-51.

Wenbin Wu, Qing Li, Kan Wang. Solving parallelly 3-D neutron diffusion equation based on HYPRE. Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2013,47(SUPPL1):48-51. (in Chinese)

[16] 李满仓, 陈长, 姚栋, 魏彦琴, 吴文斌, 赵文博, 黄世恩, 倪东洋, 巨海涛, 郑洪涛, 秦冬, 张知竹, 汪量子, 吴磊. SARCS-4程序系统临界物理模拟实验验证. 核动力工程, 2018,39(03):166-170.

Mancang Li, Zhang Chen, Dong Yao, Yanqin Wei, Wenbin Wu, Wenbo Zhao, Shien Huang, Dongyang Ni, Haitao Ju, Hongtao Zheng, Dong Qin, Zhizhu Zhang, Liangzi Wang, Lei Wu. SARCS-4 Validation of Neutronic Code SARCS-4 by Mock-up Critical Physics Experiments. Hedongli Gongcheng/Nuclear Power Engineering, 2018,39(3):166-170. (in Chinese)

[17] 孙伟, 魏彦琴, 吴文斌, 倪东洋, 卢迪, 娄磊. 行波堆深燃耗的计算特点. 强激光与粒子束, 2017,29(03):27-31.

Wei Sun, Yangin Wei, Wenbin Wu, Dongyang Ni, Di Lu, Lei Lou. High burnup calculation characteristics of traveling wave reactor. High Power Laser and Particle Beams, 2017,29(3):36005. (in Chinese)

[18] 涂晓兰, 潘俊杰, 柴晓明, 吴文斌, 陈树, 尹强, 芦韡. 中子学栅格程序KYLIN-II可视化图形建模方法研究和工具开发. 核动力工程, 2017,38(03):126-131.

Xiaolan Tu, Junjie Pan, Xiaoming Chai, Wenbin Wu, Shu Chen, Qiang Yin, Wei Lu. Research and Development of Visual Graphic Modeling for Advanced Neutron Transport Lattice Code KYLIN-II. Hedongli Gongcheng/Nuclear Power Engineering, 2017,38(3):126-131. (in Chinese)

[19] 柴晓明, 涂晓兰, 芦韡, 卢宗健, 姚栋, 李庆, 吴文斌. 先进中子学栅格程序KYLIN-2中特征线方法模块的开发与验证. 核动力工程, 2016,37(04):154-159.

Xiaoming Chai, Xiaolan Tu, Wei Lu, Zongjian Lu, Dong Yao, Qing Li, Wenbin Wu. Development and verification and validation of MOC module in advanced neutronics lattice code KYLIN-2. Hedongli Gongcheng/Nuclear Power Engineering, 2016,37(4):154-159. (in Chinese)

[20] 倪东洋, 李满仓, 吴文斌, 孙伟. 压水堆候选耐事故包壳材料的中子经济性分析. 核动力工程, 2015,36(S2):14-16.

Dongyang Ni, Mancang Li, Wenbin Wu, Wei Sun. Neutron penalty and advantage analysis of candidate accident-tolerant cladding materials in PWRs. Hedongli Gongcheng/Nuclear Power Engineering, 2015,36:14-16. (in Chinese)

[21] 魏彦琴, 王连杰, 李庆, 陈炳德, 孙伟, 吴文斌. 铀氢锆动力堆稠密栅堆芯物理性能研究. 核动力工程, 2015,36(S2):27-29.

Yanqin Wei, Lianjie Wang, Qing Li, Bingde Chen, Wei Sun, Wenbin Wu. Study on physical performance of uranium zirconium hydride power reactor with tight lattice core. Hedongli Gongcheng/Nuclear Power Engineering, 2015,36:27-29. (in Chinese)

 

 会议文章 (Conference articles)

2021年-2023年 (From 2021 to 2023)

[1]   王志强, 郑竞超, 谢择怿, 潘依婷, 吴文斌. 基于多级并行和特征线方法的六角形中子输运模拟程序开发和优化: 2021CCF全国高性能计算学术年会（CCF HPC China 2021）, 广东珠海, 2021.

[2]   吴文斌, 于颖锐, 李松岭, 秦冬, 巨海涛, 姚栋, 罗琦. 应用GMRES算法加速逐层面耦合功率扩展方法: 第十八届反应堆数值计算与粒子输运学术会议暨2020年反应堆物理会议, 陕西西安, 2020.

[3]   刘召远, 梁金刚, 吴文斌, 武鲁, 赵志刚, 刘弢. 多群蒙特卡罗模拟中负截面的抽样方法: 第十五届全国蒙特卡罗方法及其应用学术交流会, 山东济南, 2021.

[4]   郑竞超, 黄达宇, 王志强, 谢择怿, 吴文斌. 基于三维特征线方法的板型堆计算研究: 国家能源核电软件重点实验室2022-2023年学术交流会暨学术年会, 珠海, 2023.

[5]   王志强, 郑竞超, 赵晨, 彭星杰, 吴文斌. 基于特征线方法的旋转对称边界条件研究: 国家能源核电软件重点实验室2022-2023年学术交流会暨学术年会, 珠海, 2023.

[6]   黄达宇, 王志强, 郑竞超, 谢择怿, 吴文斌. 基于特征线方法的转鼓反应性控制计算研究: 国家能源核电软件重点实验室2022-2023年学术交流会暨学术年会, 珠海, 2023.

[7]   刘志华, 黄达宇, 钟一鸣, 王志强, 郑竞超, 谢择怿, 吴文斌. 高保真中子输运 CSG 建模三维可视化研究: 第十九届反应堆数值计算与粒子输运学术会议暨 2023 年反应堆物理会议, 上海, 2023.

 

2010年-2020年 (From 2010 to 2020)

 [1]  Wenbin Wu, Guillaume Giudicelli, Kord Smith, Benoit Forget, Dong Yao, Qi Luo. Improvement of CMFD acceleration capability of OpenMOC: The International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering(M&C2019), Portland, Oregon, USA, 2019.

 [2]  Wenbin Wu, Yingrui Yu, Qing Li. Verification of the 2D/1D coupling 3D transport code TIGER with C5G7 benchmark: International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C2017), Jeju, South Korea, 2017.

 [3]  Wenbin Wu, Yingrui Yu, Qing Li. Calculation of higher eigenpairs of the transport equation Using IRAM based on domain decomposition: 2017 Transactions of the American Nuclear Society, ANS 2017, June 11, 2017 - June 15, 2017, San Francisco, CA, United states, 2017. American Nuclear Society.

 [4]  吴文斌, 于颖锐, 李庆. 基于大规模并行计算的三维多群中子扩散方程有限差分方法研究: 第十六届反应堆数值计算与粒子输运学术会议暨2016年反应堆物理会议（CORPHY2016）, 中国北京, 2016.

Wenbin Wu, Yingrui Yu, Qing Li. Research on finite difference method for 3D multi-group neutron diffusion equation based on large-scale parallel computation: CORPHY2016, Beijing, 2016. (in Chinese)

 [5]  Wenbin Wu, Qing Li, Kan Wang. 2-D/1-D method for neutron transport based on large-scale parallel computation: 2014 ANS Winter Meeting and Nuclear Technology Expo, November 9, 2014 - November 13, 2014, Anaheim, CA, United States, 2014. American Nuclear Society.

 [6]  吴文斌, 李庆, 王侃. 基于大规模并行计算的2D/1D耦合三维全堆输运程序Tiger-3D: 第十五届反应堆数值计算与粒子输运学术会议暨2014年反应堆物理会议（CORPHY2014）, 中国成都, 2014.

Wenbin Wu, Qing Li, Kan Wang. Tiger-3D: 2D/1D coupled whole-core transport code based on large-scale parallel computation: CORPHY2014, Chengdu, China, 2014. (in Chinese)

 [7]  吴文斌. 结合多群GMRES的IRAM算法用于求解矩阵MOC方程: 中国核学会2013年学术年会, 中国黑龙江哈尔滨, 2013.

Wenbin Wu, Kan Wang, Qing Li. IRAM combined with multi-group GMRES for solving Matrix MOC: Annual meeting of China Nuclear Association, Harbin, China, 2013. (in Chinese)

 [8]  Wenbin Wu, Kan Wang, Qing Li. Matrix method of characteristics based on modular ray tracing: 2013 21st International Conference on Nuclear Engineering, ICONE 2013, July 29, 2013  -  August 2, 2013, Chengdu, China, 2013. American Society of Mechanical Engineers (ASME).

 [9]  吴文斌, 王侃, 李庆. 一维平板的并行SN计算方法: 核反应堆系统设计技术国家级重点实验室2010年学术交流会议, 中国成都, 2010.

Wenbin Wu, Kan Wang, Qing Li. Parallel SN method for 1D slab problem: Annual Meeting of Science and Technology on Reactor System Design Technology Laboratory, 2010. (in Chinese)

[10] Guillaume Giudicelli, Wenbin Wu, Kord Smith, Benoit Forget. Adding a Third Level of Parallelism to OpenMOC, an Open Source Deterministic Neutron Transport Solver: The International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering(M&C2019), Portland, Oregon, USA, 2019.

[11] Xiaoming Chai, Xiaolan Tu, Wei Lu, Zongjian Lu, Dong Yao, Qing Li, Wenbin Wu. The powerful method of characteristics module in advanced neutronics lattice code KYLIN-2, 2017. American Society of Mechanical Engineers (ASME).

  

发明专利

 [1]  徐飞, 吴文斌, 明平洲, 赵晨, 罗琦, 姚栋, 于颖锐, 柴晓明. 一种基于区域分解并行的广义粗网有限差分加速方法:

 [2]  吴屈, 于颖锐, 李庆, 彭星杰, 赵文博, 刘琨, 吴文斌, 龚禾林. 一种临界硼浓度搜索的方法及设备:

 [3]  徐飞, 吴文斌, 明平洲, 赵晨, 罗琦, 姚栋, 于颖锐, 柴晓明. 基于区域分解获取堆芯中子标通量的方法:

 [4]  吴屈, 于颖锐, 李庆, 彭星杰, 吴文斌, 唐霄, 柴晓明, 涂晓兰. 一种加速求解广义共轭中子输运方程的方法:

 [5]  吴文斌, 罗琦, 姚栋, 赵文博, 于颖锐, 柴晓明, 李庆. 适应现代超级计算机硬件架构的特征线法多级并行方法:

 [6]  吴文斌, 罗琦, 姚栋, 赵文博, 于颖锐, 柴晓明, 李庆. 一种基于特征线法的组合几何中子输运处理方法及装置:

 [7]  刘同先, 于颖锐, 李天涯, 肖鹏, 秦雪, 谢运利, 甯忠豪, 巨海涛, 汪量子, 吴文斌. 一种换料堆芯安全性评价方法:

 [8]  姜乃斌, 闵光云, 吴文斌, 李捷, 马宇, 王亚辉. 一种大型压水堆堆芯结构流致振动的数字反应堆仿真分析方法:

 [9]  姜乃斌, 闵光云, 李捷, 吴文斌, 马宇, 王亚辉. 一种基于数据驱动的堆内流场流动特征和流体激励仿真方法:

[10] 姜乃斌, 梁立创, 吴文斌, 李捷. 一种分区布置的石墨基弥散燃料热管堆堆芯结构:

[11] 吴文斌, 王志强, 郑竞超, 姜乃斌, 李捷, 马宇, 王亚辉. 一种中子输运特征线方法的对称边界处理方法及系统:

[12] 吴文斌, 郑竞超, 王志强, 谢择怿, 潘依婷, 姜乃斌, 李捷, 马宇, 王亚辉. 一种六角形堆芯MOC并行计算的通信优化方法及系统:

[13] 吴文斌, 姜乃斌, 李捷, 马宇, 王亚辉. 一种基于特征线的空间区域分解并行加速方法及系统:

 

 软件著作权

[1]   基于特征线方法的六角形中子输运模拟软件COREMOC-HEX.

[2]   全堆芯物理热工耦合可视化图形建模软件.

[3]   反应堆物理全堆芯可视化图形建模软件.

[4]   二维特征线追踪软件.

[5]   先进栅格（组件）中子输运计算软件.