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
2018-12~现在, 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] 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.
[2] 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.
[3] 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.
[4] 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.
[5] 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.
[6] 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: CN108198635B, 2019-07-30.
[7] 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. 中国: CN108511088A, 2018.09.07.
[8] 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. 中国: CN108172318A, 2018-06-15.

出版信息

(1) Jianhui Wu, Chunyan Zou, Chenggang Yu, Xiangzhou Cai, Jingen Chen*. Study of natural uranium utilization in a heavy water moderated molten salt reactor. Progress in Nuclear Energy, 2022, 146: 104144.

(2) Jianhui Wu, Jingen Chen*, Chunyan Zou, Chenggang Yu, Xiangzhou Cai, Yapeng Zhang. Transition to thorium fuel cycle on a heavy water moderated molten salt reactor by using low enrichment uranium. Annals of Nuclear Energy, 2022, 165: 108638.

(3) 伍建辉, 余呈刚, 邹春燕, 马玉雯, 贾国斌, 蔡翔舟, 陈金根*. 新型重水慢化熔盐堆堆芯优化设计. 核技术2021, 44 (8): 080601.

(4) Jianhui Wu, Chenggang Yu , Chunyan Zou, , Guobin Jia, Xiangzhou Cai, Jingen Chen*. Influence of reprocessing separation efficiency on the fuel cycle performances for a heavy water moderated molten salt reactor. Nuclear Engineering and Design, 2021, 380: 111311.

(5) Jianhui Wu, Yuwen Ma, Chenggang Yu, Xiangzhou Cai*, Jingen Chen*. Nuclear non-proliferation review and improving proliferation resistance assessment in the future. International Journal of Energy Research, 2020, 45:1238312395.

(6) Jianghui Wu, Jingen Chen*, Xuzhong Kang, Xiaoxiao Li, Chenggang Yu, Chunyan Zou, Xiangzhou Cai*. A novel concept for a molten salt reactor moderated by heavy water. Annals of Nuclear Energy, 2019, 132: 391-403.

(7) Jianghui Wu, Jingen Chen*, Chenggang Yu, Chunyan Zou, Yuwen Ma, Xiaoxiao Li, Xiangzhou Cai. 149Sm evolution behavior in a small modular molten salt reactor. Annals of Nuclear Energy, 2018, 120: 100-107.

(8) Jianhui Wu, Chen Guo, Xiangzhou Cai, Chenggang Yu, Chunyan Zou, Jianlong Han, Jingen Chen*. Flow effect on I-135 and Xe-135 concentration in a molten salt reactor. Nuclear Engineering and Design, 2017, 314: 318-325.

(9) Jianhui Wu, Xiaoxiao Li, Jifeng Hu, Jingen Chen*, Chenggang Yu, Chunyan Zou, Xiangzhou Cai. Influence of Xe-135 dynamic behavior on core operation safety for a molten salt reactor. ICONE26-82352, 2018, V003T02A050.

(10) Jianhui Wu, Jingen Chen*, Xiangzhou Cai, Chenggang Yu, Chunyan Zou, Xiaoxiao Li, Jianlong Han. TMSR fuel cycle evaluation under a screening and decision-making framework. ICONE25-67283, 2017, V007T10A024.

(11) Jianhui Wu, Jingen Chen. Flow Effect on Core Burnup in a Molten Salt Reactor. Proceedings of PBNC, 2017.

(12) Jianhui Wu, Yoshiaki Oka. Subchannel analysis with turbulent mixing rate of supercritical pressure fluid. Nuclear Engineering and Design, 2015, 287: 119-130.

(13) Jianhui Wu, Yoshiaki Oka. Core design of super LWR with double tube water rods. Nuclear Engineering and Design, 2014, 269: 340-348.

(14) Jianhui Wu, Nobuhiro Maekawa, Yoshiaki Oka. Single-pass core design of a low-temperature Super LWR. Journal of Nuclear Science and Technology, 2013, 50(12): 1129-1138.

(15) Jianhui Wu, Yoshiaki Oka. Improved single pass core design for high temperature Super LWR. Nuclear Engineering and Design, 2013, 267: 100-108.

(16) Jianhui Wu, Yoshiaki Oka. Single pass core design of Super LWR. Transactions of the American Nuclear Society, 2013, 109: 1105-1107.

(17) 伍建辉, 刘郁纪,李公平,等.  ART算法重建图像的影响因素. 无损检测, 2010, 32(12): 930-934.

(18) 伍建辉, 李公平, . 锥束CT扫描方式对ART算法图像重建的影响研究. 核技术, 2011, 10: 41-46. 

(19)  Yapeng Zhang, Jianhui Wu*, Jingen Chen*, Xiangzhou Cai. 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, 45: 12383-12395.

(20) Ao Zhang, Ming Dai, Maosong Cheng, Jianhui Wu*, Chunyan Zou, Yong Cui, Jingen Chen*. Rasterized coarse mesh finite difference acceleration on method of characteristics for a reactor core with a generalized boundary. Annals of Nuclear Energy, 2021, 162:108483.

(21) Chunyan Zou, Xiangzhou Cai, Chenggang Yu, Jianhui Wu*, Jingen Chen*. Transition to thorium fuel cycle for TMSR. Nuclear Engineering and Design, 2018, 330: 420-428.

(22) Chenggang Yu, Long He, Chunyan Zou, Yuwen Ma, Xiangzhou Cai, Jianhui Wu*, Jingen Chen*. Th-U breeding performance in a Channel-type molten salt Fast reactor with different starting fuels. Annals of Nuclear Energy, 2018, 122: 91-100.

(23) Shaopeng Xia, Jingen Chen, Wei Guo, Deyang Cui, Jianlong Han, Jianhui Wu*, Xiangzhou Cai*. Development of a Molten Salt Reactor specific depletion code MODEC. Annals of Nuclear Energy, 2019, 124: 88-97.

(24) 贾国斌, 伍建辉*, 陈金根, 顾国祥,蔡翔舟*,戴叶. 基于DragonDonjon程序的液态熔盐实验堆临界计算与分析. 原子能科学技术, 2019, 53(5): 853-862.

(25) Sutanto*, Jianhui Wu*. Control System of a Super-Fast Reactor with Single Flow Pass Core. International Journal on Advanced Science, Engineering and Information Technology, 2018, 8(5).

(26) 马玉雯, 陈金根, 蔡翔舟, 伍建辉*, 李晓晓, 余呈刚, 邹春燕, 杨璞*. 小型模块化钍基熔盐堆防核扩散性能初步定量评估. 原子能科学技术, 2018, 52 (11): 1994-2000.

(27) Chunyan Zou, Chenggang Yu, Jianhui Wu, Xiangzhou Cai, Jingen Chen*. Parametric study on minor actinides transmutation in a graphite-moderated thorium-based molten salt reactors. International Journal of Energy Research, 2021, 45:7840–7850.

(28) 贾国斌, 戴叶*, 伍建辉, 陈金根, 顾国祥,蔡翔舟*. 液态熔盐热堆燃料管理方法研究与分析. 原子能科学技术, 2021, 55(3): 464-473.

(29) Fan Zhu, Bin Deng, Jianhui Wu, Chenggang Yu*, Jingen Chen*, Xiang-zhou Cai. Three dimensional steady-state neutronics/thermal-hydraulics coupled simulation for a molten salt reactor moderated by zirconium hydride rods. International Journal of Energy Research, 2021:1-25.

(30) 贾国斌, 戴叶*, 伍建辉, 陈金根, 顾国祥, 蔡翔舟*. 氟盐冷却球床高温堆燃料管理程序的开发与分析. 原子能科学技术, 2021, 55(2): 286-295.

(31) 朱帆, 伍建辉, 余呈刚, 马玉雯*, 陈金根*, 蔡翔舟. 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. 原子能科学技术, 2020, 11: 2063-2072.

(32) Yapeng Zhang, Yuwen Ma*, Jianhui Wu, Jingen Chen*, Xiangzhou Cai. Preliminary analysis of fuel cycle performance for a small modular heavy water-moderated thorium molten salt reactor. Nuclear Science and Techniques, 2020, 31: 108.

(33) Jun Zhou, Jingen Chen*, Jianhui Wu, Shaopeng Xia, Chunyan Zou*. Influence of 7Li enrichment on Th-U fuel breeding performance for molten salt reactors under different neutron spectra. Progress in Nuclear Energy, 2020, 120: 103213.

(34) Ao Zhang, Chunyan Zou*, Jianhui Wu, Shaopeng Xia, Chengyang Yu, Jingen Chen*. Radiotoxicity of minor actinides in thermal, epithermal and fast TMSRs with very high burnup. Annals of Nuclear Energy, 2020, 137: 107162.

(35) Chunyan Zou, Chenggang Yu, Jianhui Wu, Xiangzhou Cai, Jingen Chen*. Transition to thorium fuel cycle in a small modular molten salt reactor based on a batch reprocessing mode. Annals of Nuclear Energy, 2020, 138: 107163.

(36) Chenggang Yu, Chunyan Zou, Chen Wu, Jianhui Wu, Xiangzhou Cai, Jingen Chen*. Sustainable supply of 99Mo source in a 2 MW molten salt reactor using low-enriched uranium. Applied Radiation and Isotopes, 2020, 160: 109134.

(37) Chengang Yu, Xiaohe Wang, Chen Wu, Chunyan Zou, Jianhui Wu, Xiangzhou Cai, Jingen Chen*. Supply of I-131 in a 2 MW molten salt reactor with different production methods. Applied Radiation and Isotopes, 2020, 166: 109350.

(38) 朱帆, 伍建辉, 陈金根*, 蔡翔舟, 余呈刚, 崔德阳, 彭一鹏. 棒状氢化锆慢化钍基熔盐堆中子学性能优化. 原子能科学技术, 2018, 52(9): 1656-1664.

(39) 继峰, , 伍建辉, 建龙,. 熔盐堆钍铀、铀钚燃料循环核数据不确定度分析. 原子能科学技术, ,2018, 52 (7):1207-1213.

(40) Chenggang Yu, Xiaoxiao Li, Xiangzhou Cai, Chunyan Zou, Yuwen Ma, Jianhui Wu, Jianlong Han, Jingen Chen*. Minor actinide incineration and Th-U breeding in a small FLiNaK Molten Salt Fast Reactor. Annals of Nuclear Energy, 2017, 99: 335-344.

(41) 李晓晓, 伍建辉,余**. 小型模块化熔盐堆钍利用方案. 原子核物理评论, 2017, 34(3): 672-676.


科研活动

   
科研项目
( 1 ) 熔盐堆动态燃耗行为研究, 主持, 国家级, 2020-01--2022-12
( 2 ) 新型重水慢化熔盐堆安全特性研究, 主持, 省级, 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, 主持, 国家级, 2020-11--2023-10
参与会议
(1)新型重水慢化熔盐堆设计及燃料循环研究   第十届反应堆物理与核材料学术研讨会   2021-04-25
(2)新型重水慢化熔盐堆(HW-MSR)钍铀循环研究   第十六届(2020年)核技术应用学术交流会   2020-12-02
(3)熔盐堆燃料流动对核素演化影响研究   2020年核物理联合学术交流会   2020-01-08
(4)TMSR (Thorium based Molten Salt Reactor) fuel cycle comprehensive evaluation   ASTM 核燃料循环国际研讨会   2019-06-11
(5)Influence of Xe-135 dynamic behavior on core operation safety for a molten salt reactor   第26届国际核工程大会   2018-07-22
(6)TMSR fuel cycle evaluation under a screening and decision   第25届国际核工程大会   2017-07-02
(7)Flow effect on core burnup in molten salt reactor   第20届太平洋地区核能大会   2016-04-05

指导学生

现指导学生

陈怡  硕士研究生  082701-核能科学与工程