董玉杰 - 清华大学 - 核能与新能源技术研究院

个人简介

教育背景学士 198907 清华大学流体力学硕士 199203 清华大学流体力学博士 199603 清华大学反应堆工程与反应堆安全工作履历 199512 - 199712 清华大学工程力学系博士后 199712 - 199808 清华大学核研院助理研究员 199808 - 200002 清华大学核研院副研究员/研究室代主任、副主任 200002 - 200106 德国于利希研究中心访问学者 200106 - 200512 清华大学核研院副研究员/研究室副主任、主任 200512 - 201010 清华大学核研院研究员/研究室主任 201010 - 至今清华大学核研院研究员（教授）/副院长奖励与荣誉 2018 中国核能行业协会科学技术奖二等奖高温堆新燃料元件运输贮存容器研制

研究领域

长期致力于模块式高温气冷堆等先进反应堆的安全特性、总体及系统技术、关键设备设计研发、仿真模拟分析等

近期论文

查看导师最新文章（温馨提示：请注意重名现象，建议点开原文通过作者单位确认）

Zhang, ZY ; Dong, YJ; Qi, WW; Sun, J. HTR-PM: Making dreams come true. NUCLEAR ENGINEERING INTERNATIONAL [J], 2019, 64(775): 16-18. Yangping Zhou, Yujie Dong, Huaqiang Yin, et al . Characterizing thermal-oxidation behaviors of nuclear graphite by combining O2 supply and micro surface area of graphite [J]. SCIENTIFIC REPORTS , 2018, 8: 13400. 薛春辉，董玉杰. 熔盐球床堆径向流堆芯的热工水力分析 [J] .核动力工程, 2018, 39(1): 12-16. 薛春辉，董玉杰. 自然循环熔盐球床堆中间换热器的优化设计 [J] .清华大学学报(自然科学版), 2018, 58(5): 445-449. Gou, F ; Liu, Y ;Chen, F B ;Dong, YJ . Thermal behavior of the HTR-10 under combined PLOFC and ATWS condition initiated by unscrammed control rod withdrawal [J]. Nuclear Science and Techniques, 2018, 29(9): 123. Gou, F ; Chen, F B ;Dong, YJ . Preliminary phenomena identification and ranking tables on the subject of the High Temperature Gas-cooled Reactor-Pebble Bed Module thermal fluids and accident analysis [J] . NUCLEAR ENGINEERING AND DESIGN, 2018, 332: 11-21. 陈福冰; 董玉杰; 张作义. HTR-10一回路流量变化试验的模拟 [J] .核科学与工程, 2017, 37(2): 210-214. Rui Yan, Yujie Dong, Yangping Zhou, et al . Investigation of oxidation behaviors of nuclear graphite being developed and IG- based on gas analysis [J] . JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY , 2017, 54(11): 1168-1177. Minggang Lang, Heng Xie, and Yujie Dong . Three Design Basis Accidents’ Analysis on the HTR-10GT [J] . Science and Technology of Nuclear Installations , 2017, 2017: Article ID 1686291. Sun, XM ; Dong, YJ ; Hao, PF; et al . Three-dimensional numerical simulation of quasi-static pebble flow [J]. ADVANCED POWDER TECHNOLOGY , 2017, 28(2): 499-505. Ximing Sun, Yujie Dong, Yangping Zhou, et al . Effects of reaction temperature and inlet oxidizing gas flow rate on IG-110 graphite oxidation used in HTR-PM [J]. Journal of Nuclear Science and Technology , 2016, 54(2): 196-204. Fubing Chen ？ Yujie Dong ？ Zuoyi Zhang . Post-test simulation of the HTR-10 reactivity insertion without scram [J]. Annals of Nuclear Energy , 2016, 92: 36-45. Zuoyi Zhang; Yujie Dong; Fu Li; et al . The Shandong Shidao Bay 200 MWe High-Temperature Gas-Cooled Reactor Pebble-Bed Module (HTR-PM) Demonstration Power Plant: An Engineering and Technological Innovation [J]. Engineering , 2016, 2(1): 112-118. 张睿东; 孙喜明; 董玉杰. 模块式高温气冷堆进水事故后的氢气行为分析 [J] .原子能科学技术, 2016, 50(5): 841-845. 张睿东; 孙喜明; 董玉杰. GASFLOW程序以及COM3D程序在反应堆氢气行为分析上的应用 [J] .核动力工程, 2015, 36(4): 74-78. Fubing Chen, Yujie Dong, and Zuoyi Zhang . Temperature Response of the HTR-10 during the Power Ascension Test [J]. Science and Technology of Nuclear Installations , 2015, 2015: Article ID 302648. 谢锋，曹建主，陈志鹏，董玉杰. ＨＴＲ－１０一回路放射性石墨粉尘实验系统设计及研究 [J] .原子能科学技术, 2015, 49(4): 744-749. 吴彦楠，董玉杰，原鲲. 粗糙元对高温气冷堆中间换热器强化传热性能的影响 [J] .原子能科学技术, 2014, 48(S1): 208-212. 陈福冰，董玉杰，张作义，等. ＨＴＲ-１０主氦风机停止试验的模拟 [J] .原子能科学技术, 2014, 48(S1): 218-221. Minggang Lang, Yujie Dong . The ATWS analysis of one control rod withdraw out of the HTR-10GT core in addition with bypass valve failure [J]. NUCLEAR ENGINEERING AND DESIGN, 2013, 271: 459-464. 吴彦楠，董玉杰，原鲲. 高温堆中间换热器流道的湍流边界层与传热特性[J] .清华大学学报(自然科学版), 2013, 53(9): 1305-1309. 房超，曹建主，董玉杰. ＨＴＲ－１０一回路放射性核素在石墨上的吸附及其微观机理研究 [J] .原子能科学技术, 2012, 46(S1): 391-396. Zhang, ZY; Wu, ZX; Wang, DZ; Xu, YH; Sun, YL; Li, F; Dong, YJ . Current status and technical description of Chinese 2 x 250 MWth HTR-PM demonstration plant [J]. NUCLEAR ENGINEERING AND DESIGN, 2009, 239(7): 1212-1219. Zheng, Y ; Shi, L ;Dong, YJ . Thermohydraulic transient studies of the Chinese 200 MWe HTR-PM for loss of forced cooling accidents [J]. ANNALS OF NUCLEAR ENERGY, 2009, 36(6): 742-751. Chen, FB ; Dong, YJ ; Zheng, YH ;et al . Benchmark Calculation for the Steady-State Temperature Distribution of the HTR-10 under Full-Power Operation [J]. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2009, 46(6): 572-580. Chen, F ; Dong, Y ; Zhang, Z ; Zheng, Y . Post-test analysis of helium circulator trip without scram at 3 MW power level on the HTR-10 [J]. NUCLEAR ENGINEERING AND DESIGN, 2009, 239(6): 1010-1018. Dong, YJ ; Gao, ZY . Thermal-hydraulic feasibility analysis on uprating the HTR-PM [J]. NUCLEAR ENGINEERING AND DESIGN, 2006, 236(5-6): 510-515. Zhang, ZY; Dong, YJ; Scherer, W . Assessments of water ingress accidents in a modular high-temperature gas-cooled reactor [J]. NUCLEAR TECHNOLOGY, 2005, 149(3): 253-264. 董玉杰，王傲巍. 高温气冷堆间接联合循环热力学分析 [J] .核科学与工程, 2017, 24(3): 224-229. Dong, Y ; Unger, HM ; Frohling, W . Comparison of plant efficiencies of various power conversion systems for high-temperature reactor modules [J]. KERNTECHNIK, 2001, 66(1-2): 8-14.

学术兼职

201911 - 至今中国核学会核能动力分会常务理事 201911 - 至今中国核学会核安全分会常务理事 201502 - 至今 IAEA气冷堆技术工作组成员