基本信息
伍建辉  男  硕导  中国科学院上海应用物理研究所
电子邮件: wujianhui@sinap.ac.cn
通信地址: 上海市 嘉定区 嘉罗公路2019号
邮政编码:

研究领域

反应堆堆芯物理、热工及瞬态事故研究;

核燃料循环物理设计及综合性能评价研究;

反应堆多物理耦合方法研究;

中子探测器模拟分析与研发;

招生信息

招生专业
082701-核能科学与工程
082703-核技术及应用
招生方向
反应堆物理与燃料循环物理
多物理耦合方法
中子探测器模拟分析与研发

教育背景

2011-09--2014-09   早稻田大学   工学博士学位
2008-09--2011-07   兰州大学   理学硕士学位

工作经历

   
工作简历
2022-12~现在, 中科院上海应用物理研究所, 研究员
2018-12~2022-12,中科院上海应用物理研究所, 副研究员
2014-09~2018-12,中科院上海应用物理研究所, 助理研究员

专利与奖励

   
奖励信息
(1) 青年科技之星, 研究所(学校), 2020
专利成果
[1] 伍建辉, 蔡翔舟, 陈金根, 邹春燕, 余呈刚, 邹杨, 赵宏凯. 熔盐堆堆芯及熔盐堆系统. CN: CN113936820A, 2022-01-14.
[2] 邹春燕, 伍建辉, 余呈刚, 陈金根, 邹杨, 蔡翔舟. 一种液态熔盐堆生产Cf-252的系统及方法. CN: CN113851246A, 2021-12-28.
[3] 马玉雯, 伍建辉, 余呈刚, 陈金根, 邹杨. 一种反应堆系统防核扩散性能评估方法. CN: CN113096841A, 2021-07-09.
[4] 余呈刚, 朱贵凤, 邹春燕, 康旭忠, 伍建辉, 严睿, 陈金根, 邹杨, 蔡翔舟. 一种液态熔盐堆生产Mo-99的方法以及系统. CN: CN112863725A, 2021-05-28.
[5] 伍建辉, 马玉雯, 余呈刚, 陈金根. 一种液态熔盐堆核扩散防护系统. CN: CN112530614A, 2021-03-19.
[6] 邹春燕, 余呈刚, 伍建辉, 陈金根, 蔡翔舟, 邹杨. 液态熔盐堆超铀燃料运行固有安全性的改善方法. CN: CN111627570A, 2020-09-04.
[7] 邹春燕, 余呈刚, 伍建辉, 陈金根, 蔡翔舟, 邹杨. 超铀燃料及其制备方法和嬗变方法. CN: CN111627569A, 2020-09-04.
[8] 伍建辉, 陈金根, 马玉雯, 邹春燕, 余呈刚. 重水慢化熔盐堆堆芯及重水慢化熔盐堆系统. CN: CN108511088A, 2018-09-07.
[9] 刘亚芬, 伍建辉, 严睿, 邹杨, 陈金根. 一种钍基熔盐增殖堆堆芯. CN: CN108198635A, 2018-06-22.
[10] 伍建辉, 刘亚芬, 陈金根, 邹杨. 熔盐堆堆芯、熔盐堆系统、燃料循环系统及燃料循环方法. CN: CN108172318A, 2018-06-15.

出版信息


发表论文
(1) Core Optimization for Extending the Graphite Irradiation Lifespan in a Small Modular Thorium-Based Molten Salt Reactor, Journal of Nuclear Engineering, 2024, 第 3 作者
(2) Xenon behavior modeling for molten salt reactors by using multiple transport mechanisms, PROGRESS IN NUCLEAR ENERGY, 2024, 第 3 作者
(3) Research on Initiating Events Analysis of Small Helium-Xenon Gas Cooled Nuclear Reactor, ENERGIES, 2023, 第 2 作者
(4) Conceptual Design of a Novel Megawatt Molten Salt Reactor Cooled by He-Xe Gas, INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2023, 第 2 作者
(5) Assembly-level analysis on temperature coefficient of reactivity in a graphite-moderated fuel salt reactor fueled with low-enriched uranium, Nuclear Science and Techniques, 2023, 第 4 作者
(6) Impacts of core parameters on the capability of Cf-252 production in an MSR, ANNALS OF NUCLEAR ENERGY, 2023, 通讯作者
(7) Development of a GPU-based three-dimensional neutron transport code, ANNALS OF NUCLEAR ENERGY, 2022, 通讯作者
(8) Accident Modeling and Analysis of Nuclear Reactors, ENERGIES, 2022, 第 1 作者
(9) Transition to thorium fuel cycle on a heavy water moderated molten salt reactor by using low enrichment uranium, ANNALS OF NUCLEAR ENERGY, 2022, 第 1 作者
(10) Study of natural uranium utilization in a heavy water moderated molten salt reactor, Progress in Nuclear Energy, 2022, 第 1 作者
(11) A Review of Molten Salt Reactor Multi-Physics Coupling Models and Development Prospects, ENERGIES, 2022, 第 1 作者
(12) 小型氦氙冷却反应堆事故发生频率分析研究, Accident occurrence frequency of a small helium-xenon gas cooled nuclear reactor system, 核技术, 2022, 第 1 作者
(13) Development and verification of a three-dimensional spatial dynamics code for molten salt reactors, ANNALS OF NUCLEAR ENERGY, 2022, 通讯作者
(14) 新型重水慢化熔盐堆堆芯优化设计, Core design optimization for a novel heavy water moderated molten salt reactor, 核技术, 2021, 第 1 作者
(15) 液态熔盐热堆燃料管理方法研究与分析, Study and Analysis on Fuel Management Method of Liquid Molten Salt Thermal Reactor, 原子能科学技术, 2021, 第 3 作者
(16) Th-U Breeding Performances in an Optimized Molten Chloride Salt Fast Reactor, NUCLEAR SCIENCE AND ENGINEERING, 2021, 第 5 作者
(17) Parametric study on minor actinides transmutation in a graphite-moderated thorium-based molten salt reactors, INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2021, 第 3 作者
(18) Nuclear non-proliferation review and improving proliferation resistance assessment in the future, INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2021, 第 1 作者
(19) Rasterized coarse mesh finite difference acceleration on method of characteristics for a reactor core with a generalized boundary, ANNALS OF NUCLEAR ENERGY, 2021, 通讯作者
(20) Ex-core transition to thorium cycle in a small modular heavy-water moderated molten salt reactor with unchanged concentration of heavy metal nuclides in the fuel salt, INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2021, 通讯作者
(21) 氟盐冷却球床高温堆燃料管理程序的开发与分析, Fuel Management Code Development and Analysisfor Pebble Bed-fluoride Salt-cooled High Temperature Reactor, 原子能科学技术, 2021, 第 3 作者
(22) Three dimensional steady-state neutronics/thermal-hydraulics coupled simulation for a molten salt reactor moderated by zirconium hydride rods, INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2021, 第 3 作者
(23) Analyses of production capacity of Sr-89 and Sr-90 in the 2 MW molten salt reactor, APPLIED RADIATION AND ISOTOPES, 2021, 第 6 作者
(24) Influence of reprocessing separation efficiency on the fuel cycle performances for a heavy water moderated molten salt reactor, Nuclear Engineering and Design, 2021, 第 1 作者
(25) 后处理效率对熔盐堆燃料循环性能的影响, Influence of reprocessing efficiency on fuel cycle performances for molten salt reactor, 核技术, 2021, 第 2 作者
(26) Analyses of production capacity of 89Sr and 90Sr in the 2 MW molten salt reactor, APPLIED RADIATION AND ISOTOPES, 2021, 第 6 作者
(27) Preliminary analysis of fuel cycle performance for a small modular heavy water-moderated thorium molten salt reactor, Preliminary analysis of fuel cycle performance for a small modular heavy water-moderated thorium molten salt reactor, NUCLEAR SCIENCE AND TECHNIQUES, 2020, 第 3 作者
(28) Transition to thorium fuel cycle in a small modular molten salt reactor based on a batch reprocessing mode, ANNALS OF NUCLEAR ENERGY, 2020, 第 3 作者
(29) Sustainable supply of 99Mo source in a 2MW molten salt reactor using low-enriched uranium, APPLIED RADIATION AND ISOTOPES, 2020, 第 4 作者
(30) Influence of 7Li enrichment on Th-U fuel breeding performance for molten salt reactors under different neutron spectra, PROGRESS IN NUCLEAR ENERGY, 2020, 第 3 作者
(31) Supply of I-131 in a 2MW molten salt reactor with different production methods, APPLIED RADIATION AND ISOTOPES, 2020, 第 5 作者
(32) 小型模块化增殖焚烧快堆MA嬗变性能分析, Minor actinides incineration in a small modular breed and burn fast reactor, 核技术, 2020, 第 4 作者
(33) Sustainable supply of Mo-99 source in a 2 MW molten salt reactor using low-enriched uranium, APPLIED RADIATION AND ISOTOPES, 2020, 第 4 作者
(34) Influence of Li-7 enrichment on Th-U fuel breeding performance for molten salt reactors under different neutron spectra, PROGRESS IN NUCLEAR ENERGY, 2020, 第 3 作者
(35) Radiotoxicity of minor actinides in thermal, epithermal and fast TMSRs with very high burnup, ANNALS OF NUCLEAR ENERGY, 2020, 第 3 作者
(36) 棒状氢化锆慢化钍基熔盐堆燃料组件稳态核热耦合程序开发, Research on Coupling of Neutronics and Thermal-hydraulics for Fuel Assembly of Thorium Molten Salt Reactor Moderated by Zirconium Hydride Rod, 原子能科学技术, 2020, 第 2 作者
(37) Development of a Molten Salt Reactor specific depletion code MODEC, ANNALS OF NUCLEAR ENERGY, 2019, 通讯作者
(38) 基于Dragon与Donjon程序的液态熔盐实验堆临界计算与分析, Critical Calculation and Analysis of Liquid Molten Salt Experimental Reactor Based on Dragon and Donjon Codes, 原子能科学技术, 2019, 第 2 作者
(39) 钍基氟盐冷却高温堆TRISO包覆燃料颗粒结构优化分析, Optimization of TRISO fuel particle for thorium-based pebble bed fluoride salt-cooled high-temperature reactor, 核技术, 2019, 第 7 作者
(40) Thorium utilization in a small modular molten salt reactor with progressive fuel cycle modes, International Journal of Energy Research, 2019, 通讯作者
(41) A novel concept for a molten salt reactor moderated by heavy water, ANNALS OF NUCLEAR ENERGY, 2019, 第 1 作者
(42) INFLUENCE OF XE-135 DYNAMIC BEHAVIOR ON CORE OPERATION SAFETY FOR A MOLTEN SALT REACTOR, PROCEEDINGS OF THE 26TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2018, VOL 3, 2018, 第 1 作者
(43) Flow effect on core burnup in a molten salt reactor, PBNC-20, 2018, 第 1 作者
(44) Control System of a Super Fast Reactor with Single Flow Pass Core, INTERNATIONAL JOURNAL ON ADVANCED SCIENCE, ENGINEERING AND INFORMATION TECHNOLOGY, 2018, 第 2 作者
(45) Transition to thorium fuel cycle for TMSR, NUCLEAR ENGINEERING AND DESIGN, 2018, 
(46) Th-U breeding performance in a Channel-type molten salt Fast reactor with different starting fuels, ANNALS OF NUCLEAR ENERGY, 2018, 通讯作者
(47) Sm-149 evolution behavior in a small modular molten salt reactor, ANNALS OF NUCLEAR ENERGY, 2018, 第 1 作者
(48) 棒状氢化锆慢化钍基熔盐堆中子学性能优化, Neutronic Optimization of Thorium Molten Salt Reactor Moderated by Zirconium Hydride Rod, 原子能科学技术, 2018, 第 2 作者
(49) 基于SCALE的熔盐堆添料与后处理系统分析程序开发及验证, Development and Verification of Molten Salt Reactor Refueling and Reprocessing System Analysis Code Based on SCALE, 原子能科学技术, 2018, 第 3 作者
(50) 小型模块化钍基熔盐堆防核扩散性能初步定量评估, Preliminary Quantitative Proliferation Resistance Assessment of Small Modular Thorium Based MSR, 原子能科学技术, 2018, 第 4 作者
(51) 149Sm evolution behavior in a small modular molten salt reactor, ANNALS OF NUCLEAR ENERGY, 2018, 第 1 作者
(52) 熔盐堆钍铀、铀钚燃料循环核数据不确定度分析, Uncertainty Analysis of Nuclear Data for Th-U and U-Pu Fuel Cycles in Molten Salt Reactor, 原子能科学技术, 2018, 第 3 作者
(53) TMSR fuel cycle evaluation under a screening and decision, ASME, ICONE-25, 2017, 第 1 作者
(54) Flow effect on I-135 and Xe-135 evolution behavior in a molten salt reactor, NUCLEAR ENGINEERING AND DESIGN, 2017, 通讯作者
(55) Minor actinide incineration and Th-U breeding in a small FLiNaK Molten Salt Fast Reactor, ANNALS OF NUCLEAR ENERGY, 2017, 第 6 作者
(56) Flow effect on 135I and 135Xe evolution behavior in a molten salt reactor, NUCLEAR ENGINEERING AND DESIGN, 2017, 第 1 作者
(57) Subchannel analysis with turbulent mixing rate of supercritical pressure fluid, NUCLEAR ENGINEERING AND DESIGN, 2015, 第 1 作者
(58) Improved single pass core design for high temperture Super LWR, Nuclear Engineering and Design, 2014, 第 1 作者
(59) Core design of super LWR with double tube water rods, NUCLEAR ENGINEERING AND DESIGN, 2014, 第 1 作者
(60) Single-pass core design of a low-temperature Super LWR, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2013, 第 1 作者
(61) 锥束CT扫描方式对ART算法图像重建的影响研究, Effect of scanning mode of cone beam CT on the image reconstruction of ART algorithm, 核技术, 2011, 第 1 作者
(62) ART算法重建图像的影响因素, Influencing Factors of Image Reconstruction with ART Algorithm, 无损检测, 2010, 第 1 作者

科研活动

   
科研项目
( 1 ) 熔盐堆动态燃耗行为研究, 负责人, 国家任务, 2020-01--2022-12
( 2 ) 新型重水慢化熔盐堆安全特性研究, 负责人, 地方任务, 2020-07--2023-06
( 3 ) 小型氦氙冷却移动式固体核反应堆全范围安全分析技术研究-系统安全分析技术, 负责人, 国家任务, 2020-11--2023-10