吴文斌



基本信息
吴文斌，男，副教授、硕士生导师，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
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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 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
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工作经历
2014.07-2016.12，中国核动力研究设计院设计所，工程师；
2016.12-2017.12，中国核动力研究设计院设计所，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，中国核动力研究设计院设计所，高级工程师；
2020.07-至今，中山大学中法核工程与技术学院，“****”引进副教授.
Professional Experience
2014.07-2016.12，Nuclear Power Institute of China, Engineer；
2016.12-2017.12，Nuclear Power Institute of China, Senior Engineer；
2017.12-2018.12，Massachusetts Institute of Technology，Postdoctoral Researcher；
2018.12-2020.07，Nuclear Power Institute of China, Senior Engineer；
2020.07-Now，Sun Yat-sen University，Associate Professor.
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研究方向
1.????? 核反应堆物理分析与工程设计
2.????? 先进多用途堆芯研究
3.????? 数字化反应堆及核电核动力软件研发
4.????? 高保真反应堆物理数值模拟
5.????? 先进数值计算方法及高性能计算应用
6.????? 多物理耦合方法
Research Interests
1.????? nuclear reactor design
2.????? reactor physics analysis methods
3.????? high-fidelity modeling and simulation of reactor physics
4.????? advanced numerical algorithms and application
5.????? high performance computing (HPC) and application
6.????? multi-physics coupling
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科研项目
1.????? 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，中央军委装备发展部基金项目，2019年11月-2021年12月，主持
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2.????? 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，中国博士后科学基金特别资助，2019年6月-2020年12月，主持
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3.????? 扩散有限差分方法的大规模并行计算研究，中国核动力研究设计院探索基金，2015年9月-2016年12月，主持
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4.????? 基于一步法的全堆芯确定论中子学输运计算方法研究，中央军委装备发展部基金项目，2014年5月-2016年4月，子课题负责人
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5.????? 基于CPU+GPU并行的2D+1D三维全堆输运方法研究，核反应堆系统设计技术国防科技重点实验室运行基金，2012年6月-2014年7月，主持
Research Grants
1.????? Study on the double heterogeneity of dispersed fuel and poison based on 3D MOC, Key Grant of Science and Technology on Reactor System Design Technology Lab, 2019.9-2021.12, PI
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2.????? Study on Constructive Solid Geometry modeling based on Reverse Polish Notation in Method of Characteristic for neutron transport, China Postdoctoral Science Foundation Grant, 2019.6-2020.12, PI
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3.????? Study on the finite difference solution of the neutron diffusion equation based on large scale parallel computation, Exploring grant of Nuclear Power Institute of China, 2015.9-2016.12, PI
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4.????? Study on the deterministic whole-core neutron transport based on “one-step” method, Key Grant of Science and Technology on Reactor System Design Technology Lab, 2014.5-2016.4, Co-PI
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5.????? Study on the 2D/1D coupling 3D neutron transport method by hybrid CPU and GPU parallelism, Grant of Science and Technology on Reactor System Design Technology Lab, 2012.6-2014.7, PI
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学术论文 (Publication list)
期刊文章 (Journal articles)
?[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 eigen-modes 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.
[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.
[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.
[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)
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会议文章 (Conference articles)
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[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).